Recent LFTR Publications
ORNL-TM-2022-2394: 2022-08 (1.8M PDF)
Safeguards for the Lithium Fluoride Thorium Reactor: A Preliminary Nuclear Material Control and Accounting Assessment
EPRI Technical Report 3002005460: 2015-10 (6.4M PDF)
Program on Technology Innovation: Technology Assessment of a Molten Salt Reactor Design
American Scientist, vol 98: 2010-07 (2.0M PDF)
Liquid-Fluoride Thorium Reactors
The Manchester Report: 2009-10-01 (2.7M PDF)
A Search for the World’s Most Promising Solutions to Climate Change
ORNL Reports about Thorium and Molten-Salt Reactors
ORNL-6952: 1999-09 (828K PDF)
Uses For Uranium-233: What Should Be Kept for Future Needs?
ORNL-5388: 1978-12 (18.4M PDF)
Interim Assessment of the Denatured 233U Fuel Cycle
ORNL-5176: 1977-02 (4.2M PDF, 1.2M OCR)
Engineering Tests of the Metal Transfer Process from MSBR Fuel Salt
ORNL-5143: 1976-11 (1.9M PDF, 462K OCR)
Mass Transfer Coefficients between LiF-BeF2-ThF4 and Bismuth
ORNL-5132: 1976-08 (37.9M PDF, 27.6M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 29, 1976
ORNL-5078: 1976-02 (30.4M PDF, 26.3M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1975
ORNL-5047: 1975-09 (32.1M PDF, 30.7M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1975
ORNL-5018: 1974-12 (49.6M PDF, 3.7M OCR)
Program Plan for the Development of Molten-Salt Breeder Reactors
ORNL-5011: 1975-06 (17.9M PDF, 9.4M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1974
ORNL-4995: 1975-07 (18.2M PDF)
An Assessment of Industrial Energy Options Based on Coal and Nuclear Systems
ORNL-4874: 1972-12 (13.9M PDF)
Development and Construction of a Molybdenum Test Stand
ORNL-4865: 1975-10 (12.8M PDF, 13.5M OCR)
Fission Product Behavior in the MSRE
ORNL-4832: 1973-03 (36.8M PDF, 12.5M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1972
ORNL-4831: 1973-02 (6.5M PDF)
Development of the Variable-Gap Technique for Measuring the Thermal Conductivity of Fluoride Salt Mixtures
ORNL-4830: 1973-01 (9.8M PDF)
The ORNL Automated Orbital Pipe Welding Systems
ORNL-4829: 1972-11 (52.8M PDF, 18.2M OCR)
Intergranular Cracking of INOR-8 in the MSRE
ORNL-4812: 1972-08 (34.2M PDF, 3.8M OCR)
Development Status of Molten-Salt Breeder Reactors
ORNL-4782: 1972-10 (48.2M PDF, 31.5M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 29, 1972
ORNL-4762: 1972-02 (9.9M PDF)
Considerations in the Long Term Management of High-Level Active Wastes
ORNL-4728: 1972-02 (38.2M PDF, 19.5M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1971
ORNL-4676: 1971-08 (57.1M PDF, 15.3M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1971
ORNL-4674: 1972-02 (9.0M PDF, 2.1M OCR)
Reactivity Balance Calculations and Long-Term Reactivity Behavior with 235U in the MSRE
ORNL-4658: 1971-12 (23.4M PDF, 5.8M OCR)
Chemical Aspects of MSRE Operations
ORNL-4628: 1973-05 (13.8M PDF, 8.1M OCR)
ORIGEN – The ORNL Isotope Generation and Depletion Code
ORNL-4622: 1971-01 (34.4M PDF, 18.9M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1970
ORNL-4616: 1971-01 (4.6M PDF, 2.8M OCR)
Preparation and Handling of Salt Mixtures for the MSRE
ORNL-4577: 1971-08 (3.7M PDF, 3.2M OCR)
Low-Pressure Distillation of a Portion of the Fuel Carrier Salt from the MSRE
ORNL-4575: 1971-06 (4.3M PDF)
Corrosion in Polythermal Loop Systems: Part II
ORNL-4574: 1971-04 (3.6M PDF, 782K OCR)
Molten-Salt Fluoride Volatility Pilot Plant
ORNL-4548: 1970-08 (57.0M PDF, 30.3M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1970
ORNL-4541: 1971-06 (13.2M PDF, 15.7M OCR)
Conceptual Design Study of a Single-Fluid Molten-Salt Breeder Reactor
ORNL-4528: 1970-08 (6.9M PDF, 7.8M OCR)
Two-Fluid Molten-Salt Breeder Reactor Design Study
ORNL-4473: 1970-02
Encapsulation of Noble Fission Product Gases in Solid Media
ORNL-4451: 1970-07 (21.9M PDF)
Siting of Fuel Reprocessing Plants and Waste Management Facilities
ORNL-4449: 1970-02 (33.5M PDF, 12.9M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1969
ORNL-4434: 1971-01 (3.4M PDF)
Low-Pressure Distillation of Molten Fluoride Mixtures
ORNL-4415: 1972-11 (1.2M PDF, 287K OCR)
Liquid-Vapor Equilibria in LiF-BeF2 and LiF-BeF2-ThF4 Systems
ORNL-4415: 1969-12
Disposal of Solid Waste from Fuel Reprocessing by Fluidized-Bed Fluoride Volatility
ORNL-4397: 1969-06 (1.4M PDF, 2.0M OCR)
Analysis of Transients in the MSRE System with 233U Fuel
ORNL-4396: 1969-08 (40.6M PDF, 19.8M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1969
ORNL-4389: 1969-05 (5.5M PDF)
Gas Transport in MSRE Moderator Graphite: Parts II and III
ORNL-4371: 1969-03 (4.9M PDF)
Preparation of Enriching Salt 7LiF-233UF4 for Refueling the Molten Salt Reactor
ORNL-4345: 1969-01
Temperature Profiles within Cylinders Containing Internal Heat Sources
ORNL-4344: 1969-02 (47.0M PDF, 11.2M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1968
ORNL-4327: 1968-12 (2.8M PDF, 330K OCR)
Mechanical Properties of Artificial Graphites–A Survey Report
ORNL-4257: 1968-07 (2.1M PDF)
An EMF Study of LiF-BeF2 Solutions
ORNL-4254: 1968-08 (30.2M PDF, 11.4M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 29, 1968
ORNL-4233: 1968-02 (4.8M PDF)
Zero-Power Physics Experiments on the MSRE
ORNL-4224: 1968-11 (4.3M PDF)
Fluorination of Falling Droplets of Molten Fluoride Salt as a Means of Recovering Uranium and Plutonium
ORNL-4191: 1967-12 (42.1M PDF, 25.0M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1967
ORNL-4148: 1967-09 (3.4M PDF)
Gas Transport in MSRE Moderator Graphite: Part I
ORNL-4123: 1967-07 (3.7M PDF)
MSRE Control Elements: Manufacture, Inspection, Drawings and Specifications
ORNL-4119: 1967-07 (21.4M PDF, 4.9M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1967
ORNL-4076: 1967-03 (18.1M PDF)
Reactor Chemistry Division: Annual Progress Report for Period Ending December 31, 1966
ORNL-4069: 1967-06 (4.0M PDF)
Development of a Model for Computing 135Xe Migration in the MSRE
ORNL-4037: 1967-01 (34.1M PDF, 16.7M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1966
ORNL-3996: 1966-08 (10.5M PDF)
Design Studies of 1000 MWe Molten-Salt Breeder Reactors
ORNL-3936: 1966-06 (33.2M PDF, 19.2M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1966
ORNL-3913: 1966-03 (18.8M PDF)
Reactor Chemistry Division: Annual Progress Report for Period Ending December 31, 1965
ORNL-3872: 1965-12 (28.8M PDF, 4.2M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1965
ORNL-3812: 1965-05 (50.1M PDF, 5.9M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1965
ORNL-3804: 1965-05 (1.1M PDF)
Rare-Earth Halides
ORNL-3791: 1966-01 (9.4M PDF)
Preliminary Design Study of a Continuous Fluorination-Vacuum Distillation System for an MSBR
ORNL-3708: 1964-11 (66.4M PDF, 24.2M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending July 31, 1964
ORNL-3661: 1964-08 (2.7M PDF)
Influence of Several Metallurgical Variables on the Tensile Properties of Hastelloy N
ORNL-3626: 1964-05 (38.6M PDF, 4.9M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending January 31, 1964
ORNL-3596: 1964-06 (555K PDF)
Adaptation of the Fused-Salt Fluoride-Volatility Process to the Recovery of Uranium from Al-U Alloy Fuel
ORNL-3594: 1964-08 (7.5M PDF)
Molten-Salt Solvents for Fluoride Volatility Processing of Al-Matrix Nuclear Fuel Elements
ORNL-3593: 1964-04 (6.3M PDF)
Mechanical Properties of Some Refractory Metals and their Alloys
ORNL-3584: 1964-05 (6.0M PDF, 980K OCR)
A Potassium-Steam Binary Vapor Cycle for Nuclear Power Plants
ORNL-3544: 1964-01 (949K PDF, 124K OCR)
Reduction of UF6 Retention on Beds of MgF2 Used for Removal of TcF6
ORNL-3529: 1963-12 (34.5M PDF, 4.4M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending July 31, 1963
ORNL-3500: 1963-11-22 (2.4M PDF)
Fabrication of the Heat Exchanger Tube Bundle for the MSRE
ORNL-3495: 1963-11-22 (624K PDF)
Review of Thorium Reserves in Granitic Rock and Processing of Thorium Ores
ORNL-3494: 1963-11-14 (2.1M PDF, 1.2M OCR)
An Experimental Study of Sorption of UF6 by NaF Pellets
ORNL-3419: 1963-05 (31.5M PDF, 8.5M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending January 31, 1963
ORNL-3411: 1963-08-13 (1.3M PDF)
Review of Electronic Absorption Spectra of Molten Salts
ORNL-3391: 1963-08 (3.8M PDF)
Mixtures of Metals with Molten Salts
ORNL-3373: 1962-12 (6.4M PDF)
Thermal Analysis of Fused Salt Phase Equilibria
ORNL-3369: 1962-12 (24.7M PDF, 5.7M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1962
ORNL-3298: 1962-09 (3.6M PDF)
Recovery of PuF6 by Fluorination of Fused Fluoride Salts
ORNL-3293: 1962-10-12 (1.6M PDF)
Thermodynamic Properties of Molten-Salt Solutions
ORNL-3282: 1962-07 (26.2M PDF, 5.9M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1962
ORNL-3253: 1962-02-09 (1.9M PDF)
Corrosion of Mark-1 INOR-8 Hydrofluorinator and Mark III Nickel Fluorinator after 14 Dissolution Runs
ORNL-3144: 1961-07-11 (4.7M PDF)
Aircraft Nuclear Propulsion Program: Semiannual Progress Report for Period Ending April 30, 1961
ORNL-3215: 1961-12 (26.2M PDF, 5.2M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1961
ORNL-3124: 1961-06-01 (1.1M PDF)
INOR-8-Graphite-Fused Salt Compatibility Test
ORNL-3122: 1961-06 (34.7M PDF, 5.4M OCR)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1961
ORNL-3029: 1960-12-16 (4.6M PDF)
Aircraft Nuclear Propulsion Program: Semiannual Progress Report for Period Ending October 31, 1960
ORNL-3014: 1960-12 (8.3M PDF, 2.2M OCR)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending July 31, 1960
ORNL-2985: 1960-09 (4.7M PDF)
The Feasibility of an Unattended Nuclear Power Plant
ORNL-2982: 1961-01-20 (2.8M PDF)
Self-Diffusion of Chromium in Nickel-Base Alloys
ORNL-2973: 1960-09 (13.1M PDF, 5.1M OCR)
Molten-Salt Reactor Program: Quarterly Progress Report for Periods Ending January 31 and April 30, 1960
ORNL-2942: 1960-07-12 (3.3M PDF)
Aircraft Nuclear Propulsion Program: Semiannual Progress Report for Period Ending April 30, 1960
ORNL-2896: 1960-12 (7.6M PDF)
Phase Equilibria in Molten-Salt Breeder Reactor Fuels
ORNL-2890: 1960-03 (10.3M PDF, 4.5M OCR)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending October 31, 1959
ORNL-2840:
Aircraft Nuclear Propulsion Program: Semiannual Progress Report for Period Ending October 31, 1959
ORNL-2833: 1961-11-01 (4.3M PDF)
Corrosion Associated with Hydrofluorination in the ORNL Fluoride Volatility Process
ORNL-2832: 1961-06 (21.4M PDF)
Corrosion Associated with Fluorination in the ORNL Fluoride Volatility Process
ORNL-2799: 1959-10 (15.5M PDF, 5.0M OCR)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending July 31, 1959
ORNL-2796: 1960-03-08 (1.6M PDF)
Experimental Molten-Salt-Fueled 30 MWe Power Reactor
ORNL-2780: 1961-01-10 (2.5M PDF)
Mechanical Properties of INOR-8
ORNL-2760: 1959-08-11 (1.1M PDF)
Welding of Nickel-Molybdenum Alloys
ORNL-2751: 1959-09-16 (5.8M PDF)
Characteristics of Spherical, Homogeneous, Two-Region, Molten-Fluoride-Salt Reactors
ORNL-2749: 1959-10-13 (346K PDF)
Solubility Relations Among Rare-Earth Fluorides in Selected Molten-Salt Solvents
ORNL-2723: 1959-06 (10.9M PDF, 3.2M OCR)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending April 30, 1959
ORNL-2719: 1959-08-17
Phase Equilibria in the System UF4-ThF4 and LiF-UF4-ThF4
ORNL-2711:
Aircraft Nuclear Propulsion Program: Semiannual Progress Report for Period Ending March 31, 1959
ORNL-2684: 1959-03 (13.0M PDF, 5.9M OCR)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending January 31, 1959
ORNL-2677: 1959-09 (4.4M PDF, 447K OCR)
Aluminum Chloride as a Thermodynamic Working Fluid and Heat Transfer Medium
ORNL-2661: 1959-04 (5.0M PDF)
The Fused-Salt/Fluoride Volatility Process for Recovering Uranium
ORNL-2658: 1959-04 (5.4M PDF)
Measurements Through a Hot Cell Window Using Optical Tooling
ORNL-2634: 1958-12 (20.6M PDF)
Molten-Salt Reactor Program Status Report
ORNL-2626: 1959-01 (12.7M PDF, 9.2M OCR)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending October 31, 1958
ORNL-2605: 1959-10 (6.6M PDF)
Gas-Cooled, Molten-Salt Heat Exchanger Design Study
ORNL-2599:
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 30, 1958
ORNL-2551: 1958-09-10 (38.4M PDF, 8.8M OCR)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending June 30, 1958
ORNL-2548: 1959-11 (11.2M PDF, 7.1M OCR)
Phase Diagrams of Nuclear Reactor Materials
ORNL-2536: 1958-08-01 (3.6M PDF, 6.1M OCR)
A Zero-Power Reflector-Moderated Reactor Experiment at Elevated Temperature
ORNL-2530: 1959-11 (5.6M PDF)
Solubility and Stability of PuF3 in Fused-Alkali-Fluoride-Beryllium Fluoride Mixtures
ORNL-2524: 1959-11 (3.2M PDF)
Influence of Composition upon the 1500F Creep-Rupture Strength and Microstructure of Mo-Cr-Fe-Ni-Base Alloys
ORNL-2517: 1958-08-20 (6.5M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 31, 1958
ORNL-2474: 1958-05 (21.4M PDF, 17.8M OCR)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending January 31, 1958
ORNL-2465: 1958-11-21 (3.9M PDF)
Termination Report for Construction of the ART Facility
ORNL-2464: 1960-03-04 (4.6M PDF)
ART Removal and Disassembly
ORNL-2442: 1958-03-14 (734K PDF)
Thermal Stress Analysis of the ART Heat Exchanger Channels and Header Pipes
ORNL-2440: 1958-04-15 (13.7M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 31, 1957
ORNL-2431: 1958-02-07 (10.0M PDF, 1.3M OCR)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending October 31, 1957
ORNL-2396: 1959-11 (5.2M PDF, 6.4M OCR)
Guide to the Phase Diagrams of the Fluoride Systems
ORNL-2387: 1958-02 (53.7M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 30, 1957
ORNL-2378: 1957-12-27 (7.1M PDF, 366K OCR)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending September 1, 1957
ORNL-2376: 1957-12-10 (3.9M PDF)
ART Fuel Pump and Xenon Removal System Development, Test Evaluation, and Aircraft Application
ORNL-2374: 1957-08-28 (635K PDF)
Some Aspects of the Behavior of Fission Products in Molten-Fluoride Reactor Fuels
ORNL-2373: 1957-08-13 (1.1M PDF)
Effect of Radiation on Corrosion of Structural Materials by Molten Fluorides
ORNL-2353: 1958-04-03 (47K PDF)
Shield Plug Assembly for the ART Fuel Pumps
ORNL-2349: 1957-12-20 (2.2M PDF)
Aircraft Reactor Experiment – Metallurgical Aspects
ORNL-2348: 1958-02-15 (2.2M PDF, 5.9M OCR)
Components of the Fused-Salt and Sodium Circuits of the ARE
ORNL-2340: 1957-09-11 (55.6M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 30, 1957
ORNL-2338: 1961-01-03 (7.2M PDF)
Interim Report on Corrosion by Zirconium-Base Fluorides
ORNL-2337: 1959-03-20 (4.3M PDF)
Interim Report on Corrosion by Alkali-Metal Fluorides: Work to May 1, 1953
ORNL-2295: 1957-06-24 (6.1M PDF)
Phase Equilibrium Diagrams for Fused Salt Systems
ORNL-2278: 1957-06-28 (3.2M PDF)
Viscosity Measurements on Molten Fluoride Mixtures
ORNL-2274: 1957-07-05 (14.3M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 31, 1957
ORNL-2264: 1957-06-04 (11.3M PDF)
Inconel as a Structural Material for a High-Temperature Fused-Salt Reactor
ORNL-2221: 1957-03-26 (44.4M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 31, 1956, part 6
ORNL-2221: 1957-03-12 (14.2M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 31, 1956, part 1-5
ORNL-2199: 1957-04 (3.9M PDF)
Investigation of Fluid Flow in the ART and Other Reflector-Moderator Reactor Cores
ORNL-2198: 1957-01-31 (3.0M PDF)
Analytical and Experimental Studies of the Temperature Structure Within the ART Core
ORNL-2192: 1958-10-23 (5.4M PDF)
Optical Properties and X-Ray Diffraction Data for Some Inorganic Fluoride and Chloride Compounds
ORNL-2183: 1957-01-24 (1.2M PDF)
Dissolution of U-Zr Fuel Elements in Fused NaF-ZrF4
ORNL-2157: 1956-12 (49.5M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1956
ORNL-2156: 1957-04-26 (1.1M PDF)
Corrosion Products Formed in the Reaction Between Fused Sodium Hydroxide and Iron-Rich Alloys of Fe, Cr, and Ni
ORNL-2150: 1956-08-23 (7.3M PDF)
A Physical Property Summary for ANP Fluoride Mixtures
ORNL-2116: 1956-07-27 (4.5M PDF)
Measurement and Analysis of the Holdup of Gas Mixtures by Charcoal Traps
ORNL-2106: 1956-09 (37.6M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1956
ORNL-2103: 1956-09-21 (5.9M PDF)
Compatibility Tests of Materials for Use in Bearings, Seals, and Valves in Fused Fluoride Salts at 1200F
ORNL-2095: 1956-05 (18.9M PDF)
Design Report on the Aircraft Reactor Test
ORNL-2061: 1956-05-23 (25.7M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1956
ORNL-2048: 1956-03 (5.8M PDF)
Corrosion of Materials in Fused Hydroxides
ORNL-2012: 1956-02-20 (14.5M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1955
ORNL-1976: 1956-02-29 (943K PDF)
Steady-State Control Characteristics of Chemical-Nuclear Aircraft Power Plants
ORNL-1965: 1957-01-15 (2.9M PDF)
A Fluoride Fuel In-Pile Loop Experiment
ORNL-1956: 1956-01-11 (6.4M PDF)
Enthalpies and Heat Capacities of Solid and Molten Fluoride Mixtures
ORNL-1955: 1956-06-14 (2.7M PDF)
Fabrication of Heat Exchangers and Radiators for High-Temperature Reactor Applications
ORNL-1947: 1955-10 (35.6M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1955
ORNL-1933: 1955-09-29 (727K PDF)
Application of Temperature Solutions for Forced Convection Systems with Volume Heat Sources
ORNL-1924: 1956-02-06 (703K PDF)
A Theoretical Study of 135Xe Poisoning Kinetics in Fluid-Fueled, Gas-Sparged Nuclear Reactors
ORNL-1896: 1955-07 (48.7M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1955
ORNL-1868: 1959-04-02 (5.8M PDF)
Disassembly and Postoperative Examination of the Aircraft Reactor Experiment
ORNL-1864: 1955-04-21 (18.9M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1955
ORNL-1845: 1955-09 (19.9M PDF)
Operation of the Aircraft Reactor Experiment
ORNL-1835: 1955-01 (10.5M PDF)
Aircraft Reactor Test Hazards Summary Report
ORNL-1816: 1955-01 (43.5M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1954
ORNL-1810: 1955-10-12 (1.3M PDF)
Some Economic Aspects of Thorium Breeder Reactors
ORNL-1808: 1955-09-19 (857K PDF)
Design Calculations for a Miniature High-Temperature In-Pile Circulating Fuel Loop
ORNL-1777: 1955-02-01 (2.3M PDF)
Fused Salt Heat Transfer Part 2: Forced Convection Heat Transfer in FLiNaK
ORNL-1771: 1954-10 (26.5M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1954
ORNL-1770: 1954-11-22 (2.1M PDF)
Preliminary Critical Assemblies of the Reflector Moderator Reactor
ORNL-1769: 1954-11-15 (674K PDF, 375K OCR)
Free Convection in Fluids Having a Volume Heat Source
ORNL-1729: 1954-07 (16.8M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1954
ORNL-1721: 1954-05 (10.0M PDF)
ORNL Aircraft Nuclear Power Plant Designs
ORNL-1716: 1954-11-08 (908K PDF)
Turbulent Heat Transfer from a Molten Fluoride Salt Mixture to NaK in a Double-Tube Heat Exchanger
ORNL-1712: 1954-05-05 (260K PDF)
Optical Properties of Some Inorganic Fluoride and Chloride Compounds
ORNL-1711: 1954-05-10 (458K PDF)
Present Status of the Investigation of Aqueous Solutions Suitable for a Thorium Breeder Blanket
ORNL-1702: 1954-07-19 (1.2M PDF)
A Summary of Density Measurements on Molten Fluoride Mixtures and a Correlation for Predicting Densities
ORNL-1701: 1954-05-11 (657K PDF)
Forced Convection Heat Transfer Between Parallel Plates and in Annuli with Volume Heat Sources within the Fluids
ORNL-1692: 1954-04 (17.4M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1954
ORNL-1653: 1954-01-07 (5.4M PDF)
Enthalpies and Specific Heats of Alkali and Alkaline-Earth Hydroxides at High Temperatures
ORNL-1649: 1954-01 (25.9M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1953
ORNL-1634: 1953-10-18 (3.4M PDF)
Preliminary Critical Assembly for the Aircraft Reactor Experiment
ORNL-1615: 1953-10-22 (2.9M PDF)
Critical Experiments on Direct Cycle Aircraft Reactor
ORNL-1609: 1953-10 (17.0M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1953
ORNL-1592: 1953-08-18 (6.3M PDF)
Chemical Methods for the Separation of Lithium Isotopes
ORNL-1567: 1953-10-06 (654K PDF, 246K OCR)
Heavy Isotope Buildup in Core of 233U Breeder
ORNL-1556: 1953-07 (17.9M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1953
ORNL-1535: 1953-08-10 (3.1M PDF)
Thermodynamic and Heat Transfer Analysis of the Aircraft Reactor Experiment
ORNL-1517: 1954-01-22 (1.1M PDF)
The Moderator Cooling System for the Reflector-Moderated Reactor
ORNL-1515: 1953-04 (6.3M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1953
ORNL-1495: 1953-03 (4.2M PDF)
General Information Concerning Hydroxides
ORNL-1491: 1953-03-17 (3.8M PDF)
Corrosion by Molten Fluorides
ORNL-1490: 1953-02-27 (2.4M PDF)
General Information Concerning Fluorides
ORNL-1463: 1953-02-26 (1.1M PDF)
Methods of Fabrication of Control and Safety Element Components for the ARE and HRE
ORNL-1439: 1953-01 (22.1M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1952
ORNL-1395: 1952-12 (755K PDF, 541K OCR)
Forced Convection Heat Transfer in Pipes with Volume Heat Sources within the Fluids
ORNL-1375: 1952-11 (18.6M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1952
ORNL-1370: 1952-10 (1.4M PDF)
Turbulent Forced Convection Heat Transfer in Circular Tubes containing Molten Sodium Hydroxide
ORNL-1368: 1952-09-23 (884K PDF, 457K OCR)
Some Effects of Transmutation Products on U233 Breeder Pile Operation
ORNL-1294: 1952-08 (23.1M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1952
ORNL-1287: 1953-03-31 (1.7M PDF)
A Design Study of a Nuclear-Powered Airplane in which Circulating Fuel is Piped Directly
ORNL-1252: 1952-02-19 (2.2M PDF)
General Information Concerning Fluorides
ORNL-1234: 1952-06-02 (9.2M PDF)
Reactor Program of the Aircraft Nuclear Propulsion Project
ORNL-1227: 1952-05 (30.6M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1952
ORNL-1170: 1952-02 (35.4M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1951
ORNL-1154: 1951-12 (23.9M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1951
ANP-65:
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1951
ORNL-1030: 1951-06-19 (616K PDF, 184K OCR)
An Investigation of ThF4-Fused-Salt Solutions for Homogeneous Breeder Reactors
ANP-60: (65.5M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1951
ORNL-0980: 1951-03-27 (3.9M PDF)
Dry Fluoride Process Status Report
ORNL-0919: 1951-02-26 (25.1M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1950
ORNL-0858: 1950-12-05 (9.6M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending August 1, 1950
ORNL-0768: 1950-08-14 (7.9M PDF, 8.5M OCR)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending May 31, 1950
ORNL-0684: 1950-04-26 (981K PDF, 139K OCR)
The Atomic Powered Aircraft, January 1950
ORNL-0629: (20.4M PDF, 3.6M OCR)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending February 28, 1950
ORNL-0528: 1950-01 (3.4M PDF, 572K OCR)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending November 30, 1949
ORNL Technical Memoranda Related to the Molten-Salt Reactor Program
ORNL-TM-2009-181: 2009-08 (7.3M PDF)
An Account of ORNL’s Thirteen Nuclear Reactors
ORNL-TM-2006-114: 2006-08 (1.1M PDF)
Assessment of Nuclear Hydrogen Synergies with Energy Processes
ORNL-TM-13553: 1999-06 (4.8M PDF)
Disposition Options for Uranium-233
ORNL-TM-13552: 1998-04 (6.5M PDF)
Strategy for the Future Use and Disposition of Uranium-233
ORNL-TM-13524: 1997-11 (220K PDF)
Isotopic Dilution Requirements for 233U Criticality Safety in Processing and Disposal Facilities
ORNL-TM-13517: 1998-03 (776K PDF)
Definition of Weapons-Usable Uranium-233
ORNL-TM-13142: 1996-01 (3.5M PDF, 697K OCR)
A Descriptive Model of the MSRE After Shutdown
ORNL-TM-12925: 1995-03 (2.7M PDF)
Materials Considerations for Molten-Salt Accelerator-Based Pu Conversion Systems
ORNL-TM-12436: 1993-09
Tensile and Creep Tests on a Single Heat of Alloy 800H
ORNL-TM-12430: 1993-09
Use of the MCM for Analysis of Alloy 800H Rupture Data
ORNL-TM-12429: 1993-10
Final Analysis of ORNL Creep-Rupture and Tensile Data on 2.25 Cr-1 Mo Steel
ORNL-TM-11955: 1992-02 (3.9M PDF)
Literature Information Applicable to the Reaction of Uranium Oxides with Chlorine to Prepare Uranium Tetrachloride
ORNL-TM-11792: 1991-11 (3.4M PDF)
Reaction of Uranium Oxides with Chlorine and Carbon or CO to Prepare Uranium Chlorides
ORNL-TM-9780-V1: 1986-09 (1.8M PDF)
Nuclear Power Options Viability Study–Volume I: Executive Summary
ORNL-TM-9780-V2: 1986-09 (8.1M PDF)
Nuclear Power Options Viability Study–Volume II: Reactor Concepts, Descriptions, and Assessments
ORNL-TM-9780-V3: 1986-09 (7.6M PDF)
Nuclear Power Options Viability Study–Volume III: Nuclear Discipline Topics
ORNL-TM-9780-V4: 1986-09 (6.3M PDF)
Nuclear Power Options Viability Study–Volume IV: Bibliography
ORNL-TM-9756: 1985-09 (5.0M PDF, 1.1M OCR)
Extended Storage-in-Place of MSRE Fuel Salt and Flush Salt
ORNL-TM-9337: 1985-02
Mechanical Properties of Inconel 617 and 618
ORNL-TM-8298: 1982-12 (3.7M PDF, 336K OCR)
Thermal-Convection-Loop Study of the Corrosion of Fe-Ni-Cr Alloys by Molten
NaNO3-KNO3
ORNL-TM-7207: 1980-07 (9.1M PDF, 948K OCR)
Conceptual Design Characteristics of a Denatured Molten-Salt Reactor with Once-Through Fueling
ORNL-TM-6763: 1979-06
Molten Salt Processes Applied to Ceramic Fuels
ORNL-TM-6474: 1978-10 (11.9M PDF)
Radiological Assessment of Thorium Mining and Milling
ORNL-TM-6415: 1979-03 (8.9M PDF, 892K OCR)
Development Status and Potential Program for Development of Proliferation-Resistant Molten-Salt Reactors
ORNL-TM-6413: 1978-08 (3.6M PDF, 478K OCR)
Molten-Salt Reactors for Efficient Nuclear Fuel Utilization without Plutonium Separation
ORNL-TM-6282: 1978-04 (3.1M PDF)
Thermodynamics of Carbon in Nickel-Based Multicomponent Solid Solutions
ORNL-TM-6002: 1977-10 (5.2M PDF, 1.4M OCR)
Status of Tellurium-Hastelloy-N Studies in Molten-Fluoride Salts
ORNL-TM-5927: 1977-11 (2.2M PDF)
Expansion Potential for Existing Nuclear Power Station Sites
ORNL-TM-5920: 1978-01 (5.5M PDF, 1.6M OCR)
Status of Materials Development for Molten-Salt-Reactors
ORNL-TM-5783: 1977-05 (2.5M PDF, 863K OCR)
Compatibility Studies of Potential Molten-Salt Breeder Reactor Materials in Molten Fluoride Salts
ORNL-TM-5782: 1977-04 (4.5M PDF, 402K OCR)
The Corrosion of Type 316 Stainless Steel to Li2BeF4
ORNL-TM-5781: 1977-05 (6.8M PDF)
Corrosion of Several Metals in Supercritical Steam at 538 C
ORNL-TM-5759: 1977-04 (3.1M PDF, 609K OCR)
Distribution and Behavior of Tritium in the Coolant-Salt Technology Facility
ORNL-TM-5741: 1977-05 (1.1M PDF)
Importance of Billet Microstructure in the Hot Extrusion of 2% Ti-Hastelloy N
ORNL-TM-5697: 1977-02 (1.3M PDF)
Production of Homogeneous Titanium-Hastelloy N Alloys
ORNL-TM-5682: 1977-01 (1.4M PDF, 246K OCR)
Survey of Technology for Storage of Thermal Energy in Heat Transfer Salt
ORNL-TM-5565: 1977-01 (9.7M PDF)
Assessment of the Thorium Fuel Cycle in Power Reactors
ORNL-TM-5540: 1976-11 (9.8M PDF)
System Design Description of Forced-Convection Molten-Salt Corrosion Loops MSR-FCL-3 and MSR-FCL-4
ORNL-TM-5503: 1976-11 (5.6M PDF)
Temperature Gradient Compatibility Tests of Some Refractory Metals and Alloys in Bi and Bi-Li Solutions
ORNL-TM-5335: 1976-10 (1.9M PDF)
Heat Transfer Measurements in a Forced Convection Loop with Two Molten-Fluoride Salts
ORNL-TM-5325: 1976-04 (3.7M PDF, 364K OCR)
Evaluation of Alternate Secondary (and Tertiary) Coolants for the MSBR
ORNL-TM-5253: 1976-07 (778K PDF, 280K OCR)
Conceptual Design of a Continuous Fluorinator Experimental Facility (CFEF)
ORNL-TM-5252:
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 23
ORNL-TM-5104: 1976-03 (4.2M PDF)
A Study of Tritium Removal from Fusion Reactor Blankets of Molten-Salt and Lithium-Aluminum
ORNL-TM-5050: 1976-11 (1.7M PDF, 284K OCR)
On Nuclear Fuel, Mass Balances, Conversion Ratio, Doubling Time, and Uncertainty
ORNL-TM-4894: 1976-03 (14.9M PDF, 10.5M OCR)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 21
ORNL-TM-4870: 1976-01 (12.8M PDF, 8.1M OCR)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 20
ORNL-TM-4863: 1975-07 (5.8M PDF, 1.8M OCR)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 19
ORNL-TM-4804: 1975-04 (2.3M PDF)
A Method for Calculating the Steady-State Distribution of Tritium in an MSBR Plant
ORNL-TM-4802: 1975-06 (2.4M PDF)
The Molten-Salt Reactor Information System
ORNL-TM-4698: 1975-03 (4.8M PDF, 1.2M OCR)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 18
ORNL-TM-4552: 1974-08 (921K PDF)
Corrosion of Several Iron and Nickel-Base Alloys in Supercritical Steam at 1000F
ORNL-TM-4380: 1973-12 (6.6M PDF)
Influence of Aging on the Impact Properties of Hastelloy N
ORNL-TM-4308: 1973-03 (1.0M PDF, 304K OCR)
Density and Viscosity of Several Molten Fluoride Mixtures
ORNL-TM-4286: 1972-12 (12.6M PDF)
Alloy Compatibility with LiF-BeF2 Salts Containing ThF4 and UF4
ORNL-TM-4272: 1972-12 (13.8M PDF)
Compatibility of Brazing Alloys and the Molten Salt NaBF4-NaF at 610 C
ORNL-TM-4271: 1972-12 (6.9M PDF)
Mass Transfer Between Hastelloy-N and a Molten NaBF4 Mixture in a Thermal Convection Loop
ORNL-TM-4221: 1972-12 (2.3M PDF)
A Forced-Circulation Loop for Corrosion Studies: Hastelloy-N Compatibility with NaBF4-NaF
ORNL-TM-4210: 1976-09 (2.4M PDF, 202K OCR)
MRPP – Multi-Region Processing Plant Code
ORNL-TM-4189: 1972-12 (12.4M PDF)
Evaluation of Hastelloy-N Alloys After Nine Years Exposure to Both a Molten Fluoride Salt and Air
ORNL-TM-4188: 1972-12 (3.6M PDF)
Effect of FeF2 Addition on Mass Transfer in a Hastelloy N/LiF-BeF2-UF4 Thermal Convection Loop System
ORNL-TM-4179: 1973-05 (1.7M PDF, 418K OCR)
Improved Representation of Some Aspects of Circulating-Fuel Reactor Kinetics
ORNL-TM-4178:
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 17
ORNL-TM-4174: 1972-12 (34.2M PDF, 13.4M OCR)
Post-Irradiation Examination of Materials from the MSRE
ORNL-TM-4173: 1972-12 (7.5M PDF)
Influence of Various Alloying Additions on the Strength of Nickel-Base Alloys
ORNL-TM-4172: 1972-12 (2.3M PDF)
Corrosion of Type 304L Stainless Steel and Hastelloy-N by Mixtures of BF3, Air, and Argon
ORNL-TM-4122: 1972-12 (1.6M PDF)
Development of a Venturi-Type Bubble Generator for Use in the MSR Xenon Removal System
ORNL-TM-4079: 1973-03 (4.1M PDF)
Forced-Convection Heat-Transfer Measurements with a Molten Fluoride Mixture Flowing in a Smooth Tube
ORNL-TM-4056: 1972-12 (1.5M PDF)
The Equilibrium of Dilute UF3 Solutions Contained in Graphite
ORNL-TM-4047: 1972-12 (1.8M PDF)
Molten Salts as Blanket Fluids in Controlled Fusion Reactors
ORNL-TM-4020:
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 16
ORNL-TM-4019:
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 15
ORNL-TM-3964: 1972-12 (3.1M PDF)
Neutron-Induced Transmutation of High-Level Radioactive Waste
ORNL-TM-3963: 1972-12 (2.8M PDF, 533K OCR)
Zero Power Experiments with 233U in the MSRE
ORNL-TM-3939: 1972-12 (4.9M PDF)
MSR Component Replacements Using Remote Cutting and Welding Techniques
ORNL-TM-3884: 1972-12 (5.5M PDF, 1.5M OCR)
The Migration of a Class of Fission Products (Noble Metals) in the MSRE
ORNL-TM-3866: 1972-10 (13.8M PDF)
Corrosion and Mass Transfer Characteristics of NaBF4-NaF in Hastelloy-N
ORNL-TM-3863: 1973-01 (6.4M PDF)
Design and Operation of a Forced-Circulation Corrosion Test Facility Employing Hastelloy-N and NaBF4 Salt
ORNL-TM-3832: 1972-06 (4.3M PDF)
Design Studies of a Molten-Salt Reactor Demonstration Plant
ORNL-TM-3777: 1972-12 (1.7M PDF)
Heat Transfer Salt for High-Temperature Steam Generation
ORNL-TM-3767: 1972-05-05 (2.5M PDF, 827K OCR)
Hybrid Computer Simulation of the MSBR
ORNL-TM-3763: 1972-04 (849K PDF)
Estimated Behavior of Titanium in MSBR Chemical Processing Systems
ORNL-TM-3718: 1972-04 (6.7M PDF)
Mass Transfer Between Small Bubbles and Liquids in Cocurrent Turbulent Pipeline Flow
ORNL-TM-3609: 1971-12 (2.0M PDF)
A Study of the Adherence of Tungsten and Molybdenum Coatings
ORNL-TM-3595: 1971-12 (15.4M PDF)
Indexed Abstracts of Selected References on Molten-Salt Reactor Technology
ORNL-TM-3579: 1972-05 (5.0M PDF, 819K OCR)
Design and Cost Study of a Fluorination-Reductive Extraction-Metal Transfer Processing Plant for the MSBR
ORNL-TM-3563: 1971-11 (1.5M PDF, 163K OCR)
Availability of Natural Resources for Molten-Salt Breeder Reactors
ORNL-TM-3561: 1971-09 (932K PDF)
Remote Inspection of Welded Joints
ORNL-TM-3548: 1971-11 (842K PDF)
The Long-Term Hazard of Radioactive Wastes Produced by Enriched Uranium, U/Pu, and Th/U Fuel Cycles
ORNL-TM-3528: 1971-08 (1.7M PDF)
Solution of the Equation Describing the Interface Between Two Fluids for Volume and Pressure Between Drops
ORNL-TM-3524: 1971-10 (9.4M PDF, 3.4M OCR)
Operation of the Sampler-Enricher in the MSRE
ORNL-TM-3515: 1971-08 (639K PDF)
Status of Noble-Gas Removal and Disposal
ORNL-TM-3488: 1971-10 (3.5M PDF)
Mass Transfer Between Hastelloy-N and Haynes Alloy No. 25 in a Molten Sodium Fluoroborate Mixture
ORNL-TM-3464: 1971-10 (5.3M PDF, 766K OCR)
Xenon Behavior in the MSRE
ORNL-TM-3428: 1971-07 (1.3M PDF)
Estimated Cost of Adding a Third Salt-Circulation Loop for Controlling Tritium Migration in the 1000-MWe MSBR
ORNL-TM-3359: 1971-09 (3.8M PDF)
ROD: A Nuclear and Fuel-cycle Analysis Code for Circulating-Fuel Reactors
ORNL-TM-3352: 1972-12 (12.2M PDF, 3.2M OCR)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 10
ORNL-TM-3344: 1972-09 (9.1M PDF)
Experience with Sodium Fluoroborate Circulation in an MSRE-Scale Facility
ORNL-TM-3321: 1971-07 (3.6M PDF)
Thermal Stability of Titanium-Modified Hastelloy-N at 650 and 760 C
ORNL-TM-3303: 1971-08 (1.5M PDF)
Further Discussion of Instrumentation and Controls Development Needed for the MSBR
ORNL-TM-3259: 1972-12 (10.3M PDF, 4.2M OCR)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 9
ORNL-TM-3258: 1972-05 (8.0M PDF, 1.1M OCR)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 8
ORNL-TM-3257: 1972-02-10 (6.0M PDF, 2.0M OCR)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 7
ORNL-TM-3253: 1971-02 (2.1M PDF, 535K OCR)
MSRE Procedures for the Period Between Examination and Ultimate Disposal
ORNL-TM-3229: 1970-11 (2.6M PDF, 1.0M OCR)
Fluid Dynamic Studies of the MSRE Core
ORNL-TM-3177: 1970-11 (2.9M PDF)
Molten-Salt Breeder Experiment Design Bases
ORNL-TM-3151: 1972-08 (9.1M PDF)
A Study of Fission Products in the Molten-Salt Reactor Experiment by Gamma Spectrometry
ORNL-TM-3145: 1971-03 (6.3M PDF)
Thermal Radiation Transfer of Afterheat in MSBR Heat Exchangers
ORNL-TM-3144: 1970-09 (2.4M PDF)
Fluorine Production and Recombination in Frozen MSR Salts after Reactor Operation
ORNL-TM-3141: 1971-12 (13.0M PDF, 2.1M OCR)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 6
ORNL-TM-3140: 1971-10 (9.1M PDF, 1.5M OCR)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 5
ORNL-TM-3139: 1971-08 (21.5M PDF, 5.4M OCR)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 4
ORNL-TM-3138: 1971-05 (11.1M PDF, 4.0M OCR)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 3
ORNL-TM-3137: 1971-02 (17.7M PDF, 5.0M OCR)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 2
ORNL-TM-3102: 1971-05 (1.2M PDF, 482K OCR)
MSBR Control Studies: Analog Simulation Program
ORNL-TM-3064: 1971-01 (24.8M PDF)
Influence of Ti, Zr, and Hf Additions on the Resistance of Modified Hastelloy-N to Irradiation Damage
ORNL-TM-3063: 1971-03 (12.2M PDF)
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens – Fourth Group
ORNL-TM-3053: 1970-11 (10.4M PDF, 5.6M OCR)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 1
ORNL-TM-3041: 1973-08 (5.5M PDF)
MSRE Operator Training and Operating Techniques
ORNL-TM-3039: 1973-06 (29.4M PDF)
MSRE Systems and Components Performance
ORNL-TM-3027: 1970-06 (11.8M PDF)
Spray, Mist, Bubbles, and Foam in the MSRE
ORNL-TM-3007: 1970-06 (1.9M PDF)
An Extended Hydraulic Model of the MSRE Circulating Fuel System
ORNL-TM-3002: 1970-05 (2.4M PDF)
Reactor Power Measurement and Heat Transfer Performance in the MSRE
ORNL-TM-2999: 1970-04 (4.3M PDF)
Quality-Assurance Practices in Construction and Maintenance of the MSRE
ORNL-TM-2997: 1970-04 (1.2M PDF, 458K OCR)
Experimental Dynamic Analysis of the MSRE with 233U Fuel
ORNL-TM-2987: 1970-10 (4.7M PDF, 4.3M OCR)
Development of Fuel- and Coolant-Salt Centrifugal Pumps for the MSRE
ORNL-TM-2978: 1970-06 (2.4M PDF)
Compatibility of Fused Sodium Fluoroborate and BF3 Gas with Hastelloy-N Alloys
ORNL-TM-2974: 1970-04-07 (1.4M PDF)
Plans for Post-Operation Examination of the MSRE
ORNL-TM-2970: 1970-05 (1.0M PDF)
Calculated Radioactivity of MSRE Fuel Salt
ORNL-TM-2953: 1971-06 (5.4M PDF)
A New Approach to a Design of Steam Generators for Molten Salt Reactor Power Plants
ORNL-TM-2952: 1971-11 (3.2M PDF)
Parametric Survery of the Effects of Major Parameters of the Design of MSBR Heat Exchangers
ORNL-TM-2927: 1970-05 (2.1M PDF, 937K OCR)
Control Studies of a 1000-MWe MSBR
ORNL-TM-2858: 1970-04 (4.9M PDF)
Tensile Properties of Hastelloy-N Welded After Irradiation
ORNL-TM-2823: 1970-03 (1.9M PDF)
Frequency-Response Testing of the Molten-Salt Reactor Experiment
ORNL-TM-2815: 1971-04 (6.5M PDF)
Computer Programs for MSBR Heat Exchangers
ORNL-TM-2780: 1969-12 (6.3M PDF)
Preliminary Systems Design Description of the Salt Pump Test Stand for the MSBE
ORNL-TM-2743: 1969-12 (4.3M PDF)
Design and Construction of Core Irradiation-Specimen Array for MSRE Runs 19 and 20
ORNL-TM-2741: 1970-01 (3.4M PDF)
Catastropic Corrosion of Type 304 Stainless Steel in a System Circulating Fused Sodium Fluoroborate
ORNL-TM-2727: 1969-12 (850K PDF)
Mechanical Behavior of Artificial Graphites as Portrayed by Uniaxial Tests
ORNL-TM-2724: 1969-12 (1.2M PDF)
Compatibility of Molybdenum-Base Alloy TZM with LiF-BeF2-ThF4-UF4 at 1100 C
ORNL-TM-2712: 1969-11 (7.1M PDF)
Feasibility Study of Remote Cutting and Welding for Nuclear Plant Maintenance
ORNL-TM-2696: 1969-09-03 (1.1M PDF)
Assessment of Molten Salts as LMFBR Intermediate Coolants
ORNL-TM-2685: 1969-08 (795K PDF)
Inherent Neutron Source in MSRE with Clean 233U Fuel
ORNL-TM-2677: 1969-11 (3.9M PDF)
Management of Noble-Gas Fission-Product Wastes from Reprocessing Spent Fuels
ORNL-TM-2647: 1970-01 (15.5M PDF)
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens – Third Group
ORNL-TM-2643: 1969-08 (2.7M PDF)
Conceptual System Design Description of the Salt Pump Test Stand for the MSBE
ORNL-TM-2596: 1969-07-08 (1.1M PDF)
Fractional Crystallization Reactions in the System LiF-BeF2-ThF4
ORNL-TM-2578: 1969-08 (3.8M PDF)
Processing of the MSRE Flush and Fuel Salts
ORNL-TM-2571: 1969-07 (2.2M PDF, 742K OCR)
Theoretical Dynamic Analysis of the MSRE with 233U Fuel
ORNL-TM-2511: 1969-05 (1.2M PDF)
Materials for Molten-Salt Reactors
ORNL-TM-2490: 1969-04 (6.5M PDF)
Compatibility of Hastelloy-N and Croloy-9M with NaBF4-NaF-KBF4 Fluoroborate Salt
ORNL-TM-2489: 1969-06-02 (1.7M PDF, 956K OCR)
MSBR Control Studies
ORNL-TM-2486: 1969-03 (689K PDF, 162K OCR)
Extraction of U, Th, and Rare Earths from Molten LiF-BeF2 into Liquid Li-Bi Solutions
ORNL-TM-2483: 1969-03 (1.1M PDF)
Pre- and Post-Irradiation Mechanical Properties of Hastelloy-N Welds
ORNL-TM-2478: 1969-03 (3.4M PDF)
Design, Construction, and Testing of a Large Molten Salt Filter
ORNL-TM-2405: 1969-01 (2.3M PDF, 1.3M OCR)
Dynamic Analysis of a Salt Supercritical Water Heat Exchanger and Throttle used with MSRE
ORNL-TM-2392: 1969-01
Diffusion of Titanium in Modified Hastelloy-N
ORNL-TM-2373: 1968-12 (1.9M PDF)
Bubbles, Drops, and Entrainment in Molten Salts
ORNL-TM-2367: 1968-09-17 (2.7M PDF, 258K OCR)
The Language of Nuclear Science
ORNL-TM-2359: 1969-02 (12.9M PDF)
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens – Second Group
ORNL-TM-2335: 1969-01 (851K PDF)
Solubility of Cerium Trifluoride in Molten Mixtures of LiF, BeF2, and ThF4
ORNL-TM-2318: 1969-02-06 (1.7M PDF)
Determination of the Void Fraction in the MSRE Using Small Induced Pressure Perturbations
ORNL-TM-2316: 1968-08 (2.1M PDF)
Physical Properties of Molten-Salt Reactor Fuel, Coolant, and Flush Salts
ORNL-TM-2315: 1968-08-27 (1.4M PDF)
Measurement of Helium Void Fraction in the MSRE Fuel Salt using Neutron-Noise Analysis
ORNL-TM-2305: 1968-12 (2.8M PDF)
Postirradiation Tensile and Creep-Rupture Properties of Incoloy 800 at 700 and 760 C
ORNL-TM-2304: 1968-09 (1.2M PDF)
MSRE Design and Operations Report Part XI-A: Test Program for 233U Operations
ORNL-TM-2282: 1968-07-10 (855K PDF, 472K OCR)
Preliminary Study of a Molten-Salt Burst Reactor
ORNL-TM-2258: 1968-09 (4.7M PDF)
Irradiation Behavior of Cladding and Structural Materials
ORNL-TM-2256: 1968-06-20 (2.0M PDF, 400K OCR)
Chemical Feasibility of Fueling Molten-Salt Reactors with PuF3
ORNL-TM-2245: 1968-07-23 (1.9M PDF)
Removal of 135Xe from Circulating Fuel Salt of the MSBR by Mass Transfer to Helium Bubbles
ORNL-TM-2238: 1968-07 (577K PDF)
Proton Reaction Analysis for Lithium and Fluorine in Graphite using a Slit-Scanning Technique
ORNL-TM-2213: 1968-11 (7.6M PDF)
Design of an Engineering-Scale, Vacuum Distillation Experiment for MSR Fuel
ORNL-TM-2180: 1968-03-26 (1.0M PDF)
Electrical Conductivity of Molten Fluorides: A Review
ORNL-TM-2170: 1969-04 (3.7M PDF)
Fluoride Volatility for Recovering U and Pu from Spent UO2 Fuels
ORNL-TM-2136: 1969-02 (6.5M PDF, 1.2M OCR)
Graphite Behavior and its Effects on MSBR Performance
ORNL-TM-2111: 1968-02 (4.6M PDF)
MSRE Design and Operations Part Report V-A: Safety Analysis of Operation with 233U
ORNL-TM-2098: 1968-01-03 (3.2M PDF)
Tube Vibration in MSRE Primary Heat Exchanger
ORNL-TM-2058: 1968-01 (2.0M PDF)
Measurement of Relative Volatilities of Rare-Earth Fluorides in Mixtures of LiF and BeF2
ORNL-TM-2047: 1967-11-08 (3.6M PDF)
Containers for Molten Fluoride Spectroscopy
ORNL-TM-2043: 1968-01 (6.6M PDF)
Effects of Irradiation on the Mechanical Properties of Hastelloy N
ORNL-TM-2036: 1967-11-02 (657K PDF)
Reduction of Iron Dissolved in Molten LiF-ThF4
ORNL-TM-2032: 1967-11-01 (2.3M PDF)
Closed-Circuit Television Viewing in Maintenance of Radioactive Systems at ORNL
ORNL-TM-2029: 1967-11 (4.0M PDF)
Investigation of One Concept of a Thermal Shield for the Room Housing an MSBR
ORNL-TM-2021: 1967-05 (19.4M PDF)
Corrosion Behavior of Nickel-Molybdenum Alloys in Fused Fluoride Mixtures
ORNL-TM-1997: 1967-11 (7.4M PDF)
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens – First Group
ORNL-TM-1993: 1967-09 (2.4M PDF, 1.1M OCR)
Experience with Hi-Temp Centrifugal Pumps and their Application to MSBRs
ORNL-TM-1976: 1967-10 (1.2M PDF)
A Literature Survey of the Fluorides and Oxyfluorides of Molybdenum
ORNL-TM-1960: 1967-12 (4.6M PDF)
Operation of Molten-Salt Convection Loops in the ORR
ORNL-TM-1946: 1967-08 (4.5M PDF)
Review of Molten-Salt Reactor Physics Calculations
ORNL-TM-1933: 1967-08-30 (1.3M PDF, 1.3M OCR)
“MATEXP”, A Program for Solving ODEs by the Matrix Exponential Method
ORNL-TM-1907: 1967-07-21 (831K PDF)
Corrosion of the Volatility Pilot Plant INOR-8 Dissolver
ORNL-TM-1906: 1967-09 (863K PDF)
In- and Ex-Reactor Stress-Rupture Properties of Hastelloy N Tubing
ORNL-TM-1859: 1967-06-30 (1.7M PDF, 145K OCR)
Maintenance Development Program for MSBRs
ORNL-TM-1858: 1967-06-09 (3.6M PDF, 619K OCR)
Safety Program for MSBRs
ORNL-TM-1857: 1967-06-12 (3.6M PDF, 615K OCR)
Physics Program for MSBRs
ORNL-TM-1856: 1967-05-22 (3.2M PDF, 133K OCR)
Instrumentation and Controls Development for MSBRs
ORNL-TM-1855: 1967-06-30 (6.8M PDF, 512K OCR)
Components and Systems Development for MSBRs
ORNL-TM-1854: 1967-06 (10.7M PDF, 3.1M OCR)
Materials Development for MSBRs
ORNL-TM-1853: 1967-06-06 (8.4M PDF, 1.8M OCR)
Chemical Research and Development for MSBRs
ORNL-TM-1852: 1967-06 (4.2M PDF, 723K OCR)
Fuel and Blanket Processing Development for MSBRs
ORNL-TM-1851: 1967-06-12 (6.6M PDF, 1.8M OCR)
Summary of the Objectives, Design, and a Program of Development of MSBRs
ORNL-TM-1810: 1967-07 (1.2M PDF)
A Model for Computing the Migration of Very Short-Lived Noble Gases into MSRE Graphite
ORNL-TM-1796: 1967-03-10 (4.9M PDF)
The Reactivity Balance in the MSRE
ORNL-TM-1741: 1967-01-10 (3.9M PDF, 185K OCR)
First-Order Perturbation Theory as Used in the Multigroup Diffusion Code EXTERMINATOR-2
ORNL-TM-1730: 1967-03 (3.0M PDF)
Considerations of Low-Pressure Distillation of MSBR Fuels
ORNL-TM-1647: 1966-10-13 (2.4M PDF, 1.5M OCR)
Experimental Dynamic Analysis of the MSRE
ORNL-TM-1626: 1966-10 (2.7M PDF)
Period Measurements on the MSRE During Fuel Circulation: Theory and Experiment
ORNL-TM-1623: 1966-09-07 (3.4M PDF)
Tests of Various Particle Filters for Removal of Oil Mists and Hydrocarbon Vapor
ORNL-TM-1545: 1967-09 (8.7M PDF)
Design Study of a Heat-Exchange System for One MSBR Concept
ORNL-TM-1544: 1966-06 (921K PDF)
Solutions to the Problems of High-Temperature Irradiation Embrittlement
ORNL-TM-1543: 1966-06-01 (1.4M PDF, 272K OCR)
Removal of Protactinium from Molten Fluoride Breeder Blanket Mixtures
ORNL-TM-1467: 1966-03-24 (3.7M PDF)
Summary of Molten-Salt Breeder Reactor Design Studies
ORNL-TM-1445: 1966-04-05 (1.1M PDF)
Simulators for Training MSRE Operators
ORNL-TM-1437: 1966-04 (2.9M PDF)
A Study of Lead and Lead-Salt Corrosion in Thermal-Convection Loops
ORNL-TM-1408: 1966-04
The Welding of New Solution-Strengthened Nickel-Base Alloys
ORNL-TM-1353: 1966-02 (1.6M PDF)
Studies of the Carbon Distribution in Hastelloy-N
ORNL-TM-1341: 1966-01 (3.7M PDF)
Elevated-Temperature Mechanical Properties of Welds in a Ni-Mo-Cr-Fe Alloy
ORNL-TM-1189: 1965-06-24 (1.3M PDF)
A Technique for Calculating Frequency Response and its Sensitivity to Parameter Changes
ORNL-TM-1146: 1965-06-11 (229K PDF)
Production of a Low-Boron Heat of Hastelloy N
ORNL-TM-1129: 1965-05-07 (8.1M PDF)
Oxide Chemistry and Thermodynamics of Molten LiF-BeF2 by Equilibriation with Gaseous H2O-HF Mixtures
ORNL-TM-1070: 1965-12 (4.9M PDF, 835K OCR)
Stability Analysis of the MSRE
ORNL-TM-1060: 1965-09 (18.8M PDF, 3.2M OCR)
Molten-Salt Converter Reactor: Design Study and Power Cost Estimates for a 1000 MWe Station
ORNL-TM-1051: 1965-03-11 (747K PDF, 249K OCR)
Reconstitution of MSR Fuel by Reducing UF6 Gas to UF4 in a Molten Salt
ORNL-TM-1023: 1965-02 (1.6M PDF)
Tube Plugging in the MSRE Primary Heat Exchanger
ORNL-TM-1017: 1965-02 (1.3M PDF)
Tensile and Creep Properties of INOR-8 for the MSRE
ORNL-TM-1005: 1965-02 (819K PDF)
Effect of Elevated Temperature Irradiation on the Strength and Ductility of Hastelloy-N
ORNL-TM-0935: 1964-09-11 (2.5M PDF, 1.3M OCR)
MSRE Neutron Source Requirements
ORNL-TM-0911: 1965-01 (5.4M PDF)
MSRE Design and Operations Report Part XI: Test Program
ORNL-TM-0910: 1965-01 (12.3M PDF)
MSRE Design and Operations Report Part X: Maintenance Equipment and Procedures
ORNL-TM-0909: 1965-01 (3.4M PDF)
MSRE Design and Operations Report Part IX: Safety Procedures and Emergency Plans
ORNL-TM-0908: 1966-01 (46.0M PDF)
MSRE Design and Operations Report Part VIII: Operating Procedures
ORNL-TM-0907(rev): 1968-12-28 (5.9M PDF)
MSRE Design and Operations Report Part VII: Fuel Handling and Processing Plant (revision)
ORNL-TM-0907: 1965-01 (7.9M PDF)
MSRE Design and Operations Report Part VII: Fuel Handling and Processing Plant
ORNL-TM-0880: 1964-07
Effect of Irradiation on the Bend Transition Temperatures of Mo- and Nb-Base Alloys
ORNL-TM-0733(rev 3): 1969-07-25 (570K PDF)
MSRE Design and Operations Report Part VI: Operating Limits (Revision 3)
ORNL-TM-0733(rev 2): 1966-09-19 (380K PDF)
MSRE Design and Operations Report Part VI: Operating Limits (Revision 2)
ORNL-TM-0733(rev): 1965-08-03 (328K PDF)
MSRE Design and Operations Report Part VI: Operating Limits (Revision)
ORNL-TM-0733: 1965-01 (326K PDF)
MSRE Design and Operations Report Part VI: Operating Limits
ORNL-TM-0732: 1965-01 (20.7M PDF)
MSRE Design and Operations Report Part V: Reactor Safety Analysis Report
ORNL-TM-0730: 1965-01 (13.9M PDF)
MSRE Design and Operations Report Part III: Nuclear Analysis
ORNL-TM-0729B: 1965-01 (64.6M PDF)
MSRE Design and Operations Report Part IIB: Nuclear and Process Instrumentation
ORNL-TM-0729A: 1965-01 (42.6M PDF)
MSRE Design and Operations Report Part IIA: Nuclear and Process Instrumentation
ORNL-TM-0728: 1965-01 (40.4M PDF)
MSRE Design and Operations Report Part I: Description of Reactor Design
ORNL-TM-0611: 1963-08-27 (652K PDF, 173K OCR)
Inherent Neutron Sources in Clean MSRE Fuel Salt
ORNL-TM-0607: 1963-08-06 (176K PDF)
Mechanical Properties of INOR-8 Cast Metal
ORNL-TM-0528: 1963-05-01 (2.1M PDF)
Design and Operation of Forced-Circulation Corrosion Testing Loops with Molten Salt
ORNL-TM-0522: 1962-10-10 (5.0M PDF)
Design Studies and Cost Estimates of Two Fluoride Volatility Plants
ORNL-TM-0519: 1963-03-14 (2.6M PDF, 359K OCR)
MSRE Maintenance Proposal
ORNL-TM-0500: 1963-03-13 (4.0M PDF)
Radiation Chemistry of MSR System
ORNL-TM-0497: 1966-08-16 (2.5M PDF)
Analysis of Filling Accidents in MSRE
ORNL-TM-0458: 1962-12-14 (695K PDF)
Some Chemical Aspects of Molten-Salt Reactor Safety
ORNL-TM-0411: 1963-01-04 (1.4M PDF)
Corrosion of Nickel-Base Specimens Exposed in the Volatility Pilot Plant Mark III Fluorinator
ORNL-TM-0380: 1962-10-13 (1.5M PDF, 725K OCR)
Prediction of Effective Yields of Delayed Neutrons in MSRE
ORNL-TM-0379: 1962-10-15 (2.3M PDF)
Temperature and Reactivity Coefficient Averaging in the MSRE
ORNL-TM-0378: 1962-11-05 (3.3M PDF)
Temperatures in the MSRE Core During Steady-State Power Operations
ORNL-TM-0361: 1962-10-17 (1.7M PDF, 506K OCR)
Development of a General Method of Explicit Solution to the Nuclide Chain Equations for Digital Machine Calculations
ORNL-TM-0328: 1962-09-19 (1.6M PDF)
Corrosion Behavior of Reactor Materials in Fluoride Salt Mixtures
ORNL-TM-0326: 1962-09-19 (1.9M PDF)
Influence of Various Gaseous Environments on the Creep-Rupture Properties of Nuclear Materials for Hi-Temp Service
ORNL-TM-0291: 1962-07-05 (352K PDF)
Homogenization of MSRP Fuel Samples
ORNL-TM-0269: 1962-07-05 (5.1M PDF, 221K OCR)
576 MWt Natural Convection Molten-Salt Reactor Study
ORNL-TM-0268: 1962-07-05 (341K PDF, 227K OCR)
Experimental 5 MW Thermal Convection Molten-Salt Reactor
ORNL-TM-0262: 1962-06-27 (980K PDF)
Xenon Diffusion in Graphite in Molten-Salt Reactors
ORNL-TM-0251: 1962-05-15 (10.9M PDF)
Safety Calculations for MSRE
ORNL-TM-0203: 1962-04-06 (12.8M PDF, 1.2M OCR)
MURGATROYD–An IBM 7090 Program for the Analysis of the Kinetics of the MSRE
ORNL-TM-0202: 1969-05 (4.5M PDF)
Corrosion Behavior of Nickel-Molybdenum Alloys in Fused Fluoride Mixtures
ORNL-TM-0128: 1962-02-28 (3.9M PDF)
Development of Freeze Valve for Use in the MSRE
ORNL-TM-0080: 1961-12-06 (406K PDF)
Laboratory-Scale Demonstration of the Fused Salt Volatility Process
ORNL-TM-0079: 1962-03-27 (2.7M PDF, 894K OCR)
Water Test Development of the Fuel Pump for the MSRE
ORNL-TM-0078: 1962-10-03 (2.7M PDF, 882K OCR)
Thermal-Stress and Strain-Fatigue Analyses of the MSRE Fuel and Coolant Pump Tanks
ORNL-TM-0051: 1961-11-10
Catastropic Oxidation of High-Temperature Alloys
ORNL-NUREG-TM-12: 1977-02 (5.7M PDF)
Carbon-14 Production in Nuclear Reactors
ORNL-MIT-117: 1970-11-18 (1.6M PDF)
Removal of Tritium from MSBR Fuel
ORNL-MIT-99: 1970-03-05
(557K PDF)
Analysis and Scaleup of the Pulsed-Gas Impregnation of Graphite with Carbon
ORNL Central Files Related to the Molten-Salt Reactor Program
ORNL-CF-77-391: 1977-08-25 (6.6M PDF)
Decommissioning Study for the MSRE
ORNL-CF-72-1-1: 1972-01-28 (390K PDF)
Consideration of Possible Methods of Disposal of MSRE Salts
ORNL-CF-71-8-10: 1971-08-06 (1.2M PDF)
Review of Possible Choices of Secondary Coolants for MSRs
ORNL-CF-71-7-8: 1971-07-07 (126K PDF)
Additional Calculations of the Distribution of Tritium in the MSRE
ORNL-CF-70-10-14: 1970-10-09
Plans for the MSRE during the Period Between Examination and Ultimate Disposal
ORNL-CF-70-9-3: 1970-09-01 (1.3M PDF)
Critique of the MSRE: A Collection of Comments Submitted by Persons Associated with the Reactor
ORNL-CF-70-3-2: 1970-03-02 (1.7M PDF)
Calculation of Stresses During a Thermal Transient in an MSBR Outlet Nozzle
ORNL-CF-70-2-7: 1970-02-04 (1.5M PDF)
Tritium in the MSRE: Calculated Production Rates and Observed Amounts
ORNL-CF-68-11-18: 1968-11-12 (2.3M PDF)
Graphite for Molten-Salt Reactors
ORNL-CF-68-5-11: 1968-05-01 (4.8M PDF)
Performance of MSRE Nuclear Power Control Systems
ORNL-CF-68-3-38: 1968-03-25 (1.5M PDF)
Decay Heat Generation by Fission Products and 233Pa in a Single-Region MSR
ORNL-CF-68-1-42: 1968-01-24 (465K PDF, 653K OCR)
Protactinium Removal from MSBR Fertile Salt
ORNL-CF-67-8-10: 1967-08-01
The Program Planned for the Molten-Salt Reactor Experiment
ORNL-CF-66-2-67: 1966-02-11 (2.8M PDF)
Analysis of MSRE Zero-Power Flux Noise Using Digital Techniques
ORNL-CF-65-10-18: 1965-10-29 (1.4M PDF)
Results of Neutron Fluctuation Measurements Made During the MSRE Zero-Power Experiment
ORNL-CF-65-8-32: 1965-08-16 (4.2M PDF)
Preliminary Report on Results of MSRE Zero-Power Experiments
ORNL-CF-65-3-1: 1965-03-03 (893K PDF)
Comparison of Calculations and Uncertainties in the Temperature Coefficients of Reactivity in the MSRE
ORNL-CF-63-9-20: 1963-09-04
A Literature Survey of Thermal and Physical Properties of Molten Fluoride and Chloride Salt Mixtures
ORNL-CF-63-2-18: 1963-02-14
Modifications to Specifications for MSRE Graphite
ORNL-CF-62-11-69: 1962-11-12 (1.5M PDF)
Preliminary Equations to Describe Iodine and Xenon Behavior in the MSRE
ORNL-CF-61-12-50: 1961-12-26 (2.6M PDF)
MSRE Analog Computer Simulation of the System with a Servo Controller
ORNL-CF-61-10-39: 1961-10-11 (0.4M PDF, 117K OCR)
Delayed Neutron Losses in Circulating Fuel Reactors
ORNL-CF-61-8-86: 1961-08-18 (10.3M PDF)
Thorium Breeder Reactor Evaluation Part I: Fuel Yields and Cost of a MSBR
ORNL-CF-61-4-62: 1961-04-19 (532K PDF)
MSRE Preliminary Physics Report
ORNL-CF-60-12-111: 1960-12-13
(402K PDF)
Homogeneous Molten-Salt Reactors
ORNL-CF-60-11-108: 1960-11-30 (954K PDF)
MSRE Radiator Design
ORNL-CF-60-11-20: 1960-11-04 (1.1M PDF)
MSRE Analog Computer Simulation of a Loss-of-Flow Accident in the Secondary System
ORNL-CF-60-6-97: 1960-06-28 (569K PDF, 121K OCR)
Molten Salt Reactors: Report for 1960 Ten-Year-Plan Evaluation
ORNL-CF-60-3-31: 1960-03-15
Interim Report on Fluid-Fuel Thermal Breeder Reactors
ORNL-CF-59-12-64: 1960-01-12 (1.7M PDF)
Molten-Salt Breeder Reactors
ORNL-CF-59-8-133: 1959-08-31 (979K PDF)
Molten Salt-Graphite Compatibility Test Results
ORNL-CF-59-2-61: 1959-04-01 (1.4M PDF)
Processing of Molten Salt Power Reactor Fuel
ORNL-CF-59-1-26: 1959-01-13 (1.4M PDF)
Preliminary Study of a Graphite-Moderated Molten-Salt Power Reactor
ORNL-CF-59-1-13: 1959-02-24 (316K PDF)
Fuel Cycle Costs in a Graphite-Moderated Slightly-Enriched Fused-Salt Reactor
ORNL-CF-58-12-79: 1958-12-15 (911K PDF)
The Need for U-233 Breeding
ORNL-CF-58-10-60: 1958-10-17 (3.3M PDF)
Survey of Low-Enrichment Molten-Salt Reactors
ORNL-CF-58-10-37: 1958-10-08 (857K PDF)
U233 Breeders–Commentary and General Remarks
ORNL-CF-58-8-33: 1958-08-13 (35.8M PDF)
Screening Tests of Mechanical Pipe Joints for a Fused Salt Reactor System
ORNL-CF-58-2-46: 1958-02-05 (2.5M PDF)
A Molten-Salt Natural Convection Reactor System
ORNL-CF-58-2-40: 1958-02-18 (1.2M PDF)
Molten Salt Heat Transfer
ORNL-CF-57-12-29: 1957-12-02 (359K PDF)
Declassification of Molten Salt Reactors
ORNL-CF-57-10-41: 1957-10-10 (790K PDF)
Molten Salts for Civilian Power
ORNL-CF-57-8-7: 1957-08 (13.0M PDF)
ORSORT Study: High Performance Marine Reactor
ORNL-CF-57-6-69: 1957-05
Molten Fluoride Reactors
ORNL-CF-57-4-92: 1957-04-08 (2.1M PDF)
Maintenance of Various Reactor Types
ORNL-CF-57-4-27: 1957-12-03 (2.9M PDF, 841K OCR)
A Preliminary Study of Molten-Salt Power Reactors
ORNL-CF-57-3-31: 1957-03-08
Fused Salt Power Reactor Study: Discussion Meeting 8
ORNL-CF-57-2-65: 1957-02-14
Fused Salt Power Reactor Study: Discussion Meeting 7
ORNL-CF-57-1-135: 1957-01-30
Fused Salt Power Reactor Study: Discussion Meeting 6
ORNL-CF-57-1-57: 1957-01-17
Power Reactor Based on Fused Salt Technology
ORNL-CF-56-12-101: 1956-12-29
Fused Salt Power Reactor Study: Discussion Meeting 5
ORNL-CF-56-12-35: 1956-12-11
Fused Salt Power Reactor Study: Discussion Meeting 4
ORNL-CF-56-10-110: 1956-10-29 (1.3M PDF)
Fused Salt Power Reactor Study: Discussion Meeting 3
ORNL-CF-56-9-107: 1956-09-26
Proposal for Fused Salt Power Reactor Study Group
ORNL-CF-56-9-32: 1956-09-11
Fused Salt Power Reactor Study: Discussion Meeting 2
ORNL-CF-56-8-208: 1956-08
ORSORT Study: 600 MW Fused Salt Homogeneous Reactor Power Plant
ORNL-CF-56-8-204: 1956-08 (10.9M PDF)
ORSORT Study: Fused Salt Fast Breeder
ORNL-CF-56-7-114: 1956-07-18 (598K PDF)
Fused Salt Power Reactor Study: Discussion Meeting 1
ORNL-CF-56-5-65: 1956-05-14
Fused Salt Heat Transfer
ORNL-CF-56-4-173: 1956-04-26
Molten Salt Requirements for Pratt and Whitney Aircraft
ORNL-CF-56-3-117: 1956-03-23 Feasibility of Molten Salt Power Reactors
ORNL-CF-56-2-80: 1956-02-17
Fused Salt Processing: Problem Statement
ORNL-CF-53: 1953-08-20
ORSORT Study: Circulating Fluoride Reactor for a Submarine
ORNL-CF-53-10-25: 1953
ORSORT Study: Fused Salt Breeder Reactor
ORNL-CF-53-9-84: 1953-08-14 (12.1M PDF)
ORSORT Study: Reflector-Moderated, Circulating Fuel Aircraft Reactor
Liquid-Chloride Reactors
Dr. Eric Ottewitte, INEL: 1992-04 (5.2M PDF)
Cursory First Look at the Molten Chloride Fast Reactor as an Alternative
to the Conventional BATR Concept
Dr. Eric Ottewitte, UCLA: 1982 (11.1M PDF)
Configuration of a Molten Chloride Fast Reactor on a Thorium Fuel Cycle
to Current Nuclear Fuel Cycle Concerns
EIR-411: 1980-07 (2.2M PDF)
Reactor with Very Low Fission Product Inventory
EIR-332: 1978-01 (7.1M PDF)
Fast Reactors Using Molten Chloride Salts as Fuel: Final Report (1972-1977)
EIR-276: 1976-04
Breeding in Molten-Salt Reactors
EIR-270: 1975-02 (1.5M PDF)
Transmutation of Fission Products in a Liquid-Fuelled Fast Fission Reactor with Thermal Column
EIR-267: 1974-12 (1.1M PDF)
Chemical State of Sulphur Obtained by the
35Cl(n,p)35S Reaction
During In-Pile Irradiation
EIR-259: 1975-09 (1.3M PDF)
A High-Flux Fast Molten Salt Reactor for the Transmutation of
137Ce and 90Sr
AEEW-R956: 1974-08 (4.4M PDF, 1.4M OCR)
An Assessment of a 2500 MWe Molten Chloride Salt Fast Reactor
EIR-257: 1974-05 (1.4M PDF)
The Possibility of Continuous In-core Gaseous Extraction
of Volatile Fission Products in a Molten Fuel Reactor
EIR-249: 1974-01 (2.5M PDF)
A Molten Salt Fast Thermal Reactor System with no Waste
ANSE-1-277: 1974 (156K PDF)
Molten Plutonium Chloride Fast Breeder Reactor Cooled by Molten Uranium Chloride
NED-5-109: 1967 (397K PDF)
New Boiling Salt Fast Breeder Reactor Concepts
NA-3-540: 1967 (169K PDF)
Fuel Properties and Nuclear Performance of Fast Reactors Fueled with Molten Chlorides
NSE-23-189: 1965 (103K PDF)
Fission Product Effects in Molten Chloride Fast-Reactor Fuels
ANL-6792: 1963-10 (117K PDF)
Molten-Salt Fast Reactors
MSR-63-53: 1963-10-31 Thermodynamic Stability of Metals and Their Chlorides in the Presence of
UCl3 and PuCl3
MIT-5001: 1952-10-15 (6.3M PDF)
Chemical Problems of Non-Aqueous Fluid-Fuel Reactors
MIT-5000: 1952-10-15 (12.0M PDF)
Nuclear Problems of Non-Aqueous Fluid-Fuel Reactors
Fluoride-Salt-Cooled, Solid-Fueled Reactors
ORNL-TM-2010-199: 2010-12 (8.6M PDF)
Pre-Conceptual Design of a Fluoride-Salt-Cooled Small Modular Reactor (SmAHTR)
ORNL-TM-2006-92: 2006-06 (5.6M PDF)
Refueling Options and Considerations for Liquid-Salt-Cooled VHTRs
ORNL-TM-2006-69: 2006-06 (719K PDF)
Assessment of Candidate Molten-Salt Coolants for the NGNP/NHI Heat-Transfer Loop
ORNL-TM-2006-12: 2006-03 (1.2M PDF)
Assessment of Candidate Molten-Salt Coolants for the AHTR
Space Power Reactor Technology
ORNL-TM-2004-214: 2004-09 (3.9M PDF)
Technology Development Program for an Advanced Potassium Rankine Power Conversion System Compatible with Several Space Reactor Designs: Final Phase I Report
CONF-820814-24: 1982-08 (3.3M PDF)
Alkali Metal Rankine Topping Cycle System Design and Development
CONF-820228-1: 1982-02 (6.1M PDF)
Technological Limitations on Nuclear-Electric Space-Power Systems
ORNL-TM-6406: 1978-03 (5.3M PDF)
Potassium Vapor Topping Cycle Technical Progress Report for Period January 1, 1978 – March 31, 1978
ORNL-TM-6237: (761K PDF)
Summary of Research and Development Effort on Closed-Cycle Gas Turbines
ORNL-TM-4999: 1975-11 (3.8M PDF)
Comparative Study of the More Promising Combinations of Blanket Materials, Power Conversion Systems, and Tritium Recovery and Containment Systems for Fusion Reactors
ORNL-4025: 1968 (31.1M PDF)
The Intermediate Potassium System – A Rankine Cycle, Potassium Test Facility
ORNL-TM-2081: 1968-05-08 (2.4M PDF)
Design Studies of Condensers and Radiators for Cesium and Potassium Vapor Cycle Space Power Plants
ORNL-TM-1620: 1967
Some Calculations Performed on a Series of Conceptual Fast-Neutron Reactors Fueled with HEUO2 or PuO2
ORNL-TM-1619: 1967
Possible Control Mechanisms for the MPRE
ORNL-TM-1614
The Intermediate Water System – A Rankine Cycle Test Facility
ORNL-TM-1613
Thermal Performance of a Finned-Radiator Tube with a Reflector
ORNL-TM-1611: 1967
A Theoretical Investigation of the Dynamic Characteristics of the MPRE
ORNL-TM-1609
Development of an Entrainment Separator for the MPRE
ORNL-TM-1608
Design and Development of the MPRE Reactor Control Drive System
ORNL-TM-1491
Summary of Possible Improvements to the MPRE and of Alternate Systems
ORNL-4022
Stress Analysis of MPRE Pressure Vessel
ORNL-4018: 1966-12
Medium-Power Reactor Experiment: Quarterly Progress Report for Period Ending June 30, 1966
ORNL-TM-1413: 1966-07 (2.6M PDF)
Vapor-Bubble Growth Rates in Superheated Liquid Metals
ORNL-TM-1371: 1966 (4.7M PDF)
Analysis of the Hot Spot Problem in the MPRE
ORNL-TM-1370: (8.8M PDF)
Stability and Control Characteristics of Electrically Heated Test Rigs Designed to Simulate the MPRE Fluid System
ORNL-TM-1369
An Analog Study of a Single-Loop Rankine Cycle System
ORNL-TM-1367
Reactor Shielding for Nuclear Turbine-Generator Space Power Plants
ORNL-TM-1366
Comparison of 1, 2, and 3-Loop Systems for Nuclear Turbine-Generator Space Power Plants
ORNL-TM-1365: 1966-04
Design Study of Boiling Potassium Reactors for Thermal Outputs of 1 MW to 30 MW
ORNL-TM-1364
Survey of Operating Conditions and Requirements for Nuclear Reactor Turbine-Generator Space Power Plants
ORNL-TM-1362: 1966 (4.9M PDF)
Factors Affecting the Mechanical Properties of Stainless Steels at MPRE Operating Temperatures
ORNL-TM-1360
Comparison of Reactor Fuels for High-Temperature Applications
ORNL-TM-1344: 1966
Fuel Element Design for Boiling Potassium Reactors
ORNL-3976
Medium-Power Reactor Experiment: Quarterly Progress Report for Period Ending March 31, 1966
ORNL-3937
Medium-Power Reactor Experiment: Quarterly Progress Report for Period Ending December 31, 1965
ORNL-3902: (22.8M PDF)
MPRE Fuel Elements: Manufacture, Inspection, Drawings, and Specifications
ORNL-TM-1316: 1965-11
Compatibility of Potassium with Structural Materials
ORNL-TM-1137
The Rankine Cycle in a Zero-Gravity Environment
ORNL-TM-0898
MPRE Safety Analysis Report
ORNL-TM-0820
Medium-Power Reactor Experiment Test Facility Preliminary Design Report
ORNL-TM-0618
Notes on the Liquid-Metal Boiling Phenomenon
ORNL-TM-0602
Fabrication of Radiators for Boiling Heat-Transfer Experiments
ORNL-TM-0534
Condensing Flow in Finned, Tapered Tubes
ORNL-3897
Medium-Power Reactor Experiment: Quarterly Progress Report for Period Ending September 30, 1965
ORNL-3860
Medium-Power Reactor Experiment: Quarterly Progress Report for Period Ending June 30, 1965
ORNL-3818
Medium-Power Reactor Experiment: Quarterly Progress Report for Period Ending March 31, 1965
ORNL-3790: 1965-06
Natural Circulation Boiling Potassium Corrosion Test Loops
ORNL-3774
Medium-Power Reactor Experiment: Quarterly Progress Report for Period Ending December 31, 1964
ORNL-3748
Medium-Power Reactor Experiment: Quarterly Progress Report for Period Ending September 30, 1964
ORNL-3745: (14.0M PDF)
Performance of Experimental Jet Pumps Under Noncavitating and Cavitating Conditions
ORNL-3683
Space Power Program: Quarterly Progress Report for Period Ending June 30, 1964
ORNL-3641
Medium-Power Reactor Experiment: Quarterly Progress Report for Period Ending March 31, 1964
ORNL-3605
Thermophysical Property Measurements of Alkali Liquid Metals
ORNL-3584: 1964-05 (6.0M PDF)
A Potassium-Steam Binary Vapor Cycle for Nuclear Power Plants
ORNL-3571
Space Power Program: Semiannual Progress Report for Period Ending December 31, 1963
ORNL-3534
Medium-Power Reactor Experiment: Quarterly Progress Report for Period Ending September 30, 1963
ORNL-3489: 1963-10-11 (23.8M PDF)
Space Power Program: Semiannual Progress Report for Period Ending June 30, 1963
ORNL-3420
Space Power Program: Semiannual Progress Report for Period Ending December 31, 1962
ORNL-3337
Space Power Program: Semiannual Progress Report for Period Ending June 30, 1962
JPL-TR-32-198: 1962-03-15 (775K PDF)
A Parametric Survey of Criticality-Limited Fast Reactors Employing Uranium Fluoride Fuels
ORNL-3270
Space Power Program: Semiannual Progress Report for Period Ending December 31, 1961
ORNL-2768
A Comparative Study of Fission-Reactor-Turbine-Generator Power Sources for Space Vehicles
ORNL-CF-59-8-51: 1959-08-07 (387K PDF)
Radiators for Space Power Plants
Recent and Assorted Documents
FJOH-2004: 2004-08
Reactors with Molten Salts: Options and Missions
ICAPP-4152: 2004-06-13
An Advanced Molten Salt Reactor Using High-Temperature Reactor Technology
CTS-31-92: 1991-02-18
The MSR Option for Beneficial Use of Fissile Material from Dismantled Weapons
NSE-90-374: 1985
The Molten Salt Adventure
ORNL Review: 1969
The INOR-8 Story
ORAU-IEA-77-13: 1977
MSR Concepts with Reduced Potential for Proliferation of Special Nuclear Materials
ANL-7092: 1965-09
Catalog of Nuclear Reactor Concepts: Part I, Section III
JPL-TR-32-198: 1962-03-15
Parametric Survey of Criticality-Limited Fast Reactors Employing Uranium Fluoride Fuels
Thorium, Hydrogen, and Assorted Documents
IAEA-TECDOC-1450: 2005-05 (1.9M PDF)
Thorium Fuel Cycle–Potential Benefits and Challenges
IAEA-TECDOC-1155: 2000-05 (8.6M PDF)
Thorium-based Fuel Options for the Generation of Electricity: Developments in the 1990s
WASH-1222: 1972-09 (4.4M PDF, 274K OCR)
An Evaluation of the Molten Salt Breeder Reactor
WASH-1184: 1972-01 (2.2M PDF, 292K OCR)
Updated (1970) Cost-Benefit Analysis of the US Breeder Reactor Program
WASH-1126: 1969-04 (10.5M PDF)
Cost-Benefit Analysis of the US Breeder Reactor Program
WASH-1097: 1969-06 (1.9M PDF)
The Use of Thorium in Nuclear Power Reactors
TID-26156: 1972-02 (13.3M PDF)
Ebasco Services 1000 MWe MSBR Conceptual Design Study
SL-1954: 1962-06 (12.2M PDF)
Sargent and Lundy Capital Cost Evaluation of 1000 MWe MSCR Power Plants
TID-8507: 1959-02 (16.4M PDF)
Report of the Fluid Fuel Reactors Task Force
LA-1156: 1950-09
Lithium Separation by Electrolysis
NAS-NS-3063: 1986-02 (2.8M PDF)
The Radiochemistry of Uranium, Neptunium, and Plutonium–An Updating
NAS-NS-3060: 1974-12 (6.6M PDF)
The Radiochemistry of Neptunium
NAS-NS-3058: 1965-09 (7.3M PDF)
The Radiochemistry of Plutonium
NAS-NS-3050: 1962-03 (11.2M PDF)
The Radiochemistry of Uranium
NAS-NS-3025: 1960-10 (3.4M PDF)
The Radiochemistry of the Rare Gases
NAS-NS-3016: 1959-12 (2.4M PDF)
The Radiochemistry of Protactinium
NAS-NS-3013: 1960-05 (2.3M PDF)
The Radiochemistry of Beryllium
NAS-NS-3004: 1960-01 (2.9M PDF)
The Radiochemistry of Thorium
ORNL Reports on Solid Thorium Fuels and the Thorex Process
ORNL-4802: (7.9M PDF)
Sol-Gel Process: Engineering-Scale Demonstration of the Preparation of High-Density UO2 Microspheres
ORNL-4755: (1.7M PDF)
Conversion of uranium nitrate to ceramic-grade oxide for the light water breeder reactor: process development
ORNL-4746: (6.1M PDF)
Calculation of the Transient Behavior of a Dilute-Purex Solvent Extraction Process Having Application to the Reprocessing of LMFBR Fuels
ORNL-4637: (16.0M PDF)
Gas-Cooled Reactor and Thorium Utilization Programs semiannual progress report for period ending September 30, 1970
ORNL-4629: (6.4M PDF)
Status and Progress Report for Thorium Fuel Cycle Development for January 1, 1969–March 31, 1970
ORNL-4544: (4.3M PDF)
Engineering-Scale Demonstration of the Sol-Gel Process: Preparation of 100 kg of ThO2-UO2 Microspheres at the Rate of 10 kg/day
ORNL-4436: (19.2M PDF)
Aqueous processing of LMFBR fuels – Technical assessment and experimental program definition
ORNL-4429: (9.9M PDF)
Status and Progress Report for Thorium Fuel Cycle Development for 1967 and 1968
ORNL-4311: (1.1M PDF)
SOL-GEL thoria extrusion
ORNL-4278: (13.4M PDF)
Thorium-Uranium Recycle Facility
ORNL-4275: (11.4M PDF)
Status and progress report for thorium fuel cycle development for period ending December 31, 1996
ORNL-4218: (4.6M PDF)
Physical, mechanical, and irradiation properties of thorium and thorium alloys
ORNL-4213: (956K PDF)
Hot-Cell Evaluation of the Grind–Leach Process. Ii. Recovery of Uranium and Thorium from Irradiated Pyrolytic-Carbon-Coated Sol–Gel Thoria–Urania Particles
ORNL-4029: (4.4M PDF)
Design of a Critically Safe 233U Batch Dissolver for Building 3019
ORNL-3977: (1.5M PDF)
Oxidation and Chlorination of Uo₂-Puo₂
ORNL-3950: (5.4M PDF)
Adsorption of Protactinium on Unfired Vycor: Final Hot-Cell Experiments
ORNL-3831: (12.7M PDF)
Status and progress report for thorium fuel cycle development for period ending December 31, 1964
ORNL-3773: (561K PDF)
Adsorption of protactinium on unfired VYCOR: initial hot-cell experiments
ORNL-3611: (8.1M PDF)
Status and progress report for thorium fuel cycle development for period ending December 31, 1963
ORNL-3599: (4.5M PDF)
The Effect of Nitric Acid, Thorium, Fluoride, and Aluminum on Protactinium Adsorption by Unfired Vycor Glass
ORNL-3418: (1.7M PDF)
Aqueous processing of thorium fuels, part II
ORNL-3219: (5.4M PDF)
Aqueous processing of thorium fuels
ORNL-3155: (5.2M PDF)
Laboratory development of the acid thorex process for recovery of Consolidated Edison thorium reactor fuel
ORNL-2844: (4.2M PDF)
Thorex Pilot Plant Corrosion Studies: II, Corrosion of types 304L, 309SCb, and 347 stainless steel during development and production-development periods
ORNL-2720: (1.4M PDF)
Recovery of thorium, uranium, and rare earths rom monazite sulfate liquors by the amine extraction (AMEX) process
ORNL-2673: (11.9M PDF)
Thorex Pilot Plant corrosion studies: I. Corrosion of types 304L and 309SCb stainless steel during production and development periods
ORNL-2591: (1.3M PDF)
Laboratory Development of the Thorex Process progress report, December 1, 1955 to January 1, 1958
ORNL-2347: (709K PDF)
Chemical processing of irradiated thorium oxide status review for May 1956 to May 1957
ORNL-2332: (5.4M PDF)
A criticality study of the Thorex Pilot Plant
ORNL-2319: (6.6M PDF)
A compilation of data on some spectra of thorium
ORNL-2143: (885K PDF)
Critical mass studies, part VIII aqueous solutions of U-233
ORNL-2132: (4.1M PDF)
The organization, administration, and operation of a radiochemical pilot plant
ORNL-2126: (4.0M PDF)
The buildup of heavy isotopes during thermal neutron irradiation of uranium reactor fuels
ORNL-2102: (7.9M PDF)
Analysis of Thorex Pilot Plant radiation exposures during 1955
ORNL-2058: (6.3M PDF)
Decontamination of the ORNL Thorex Pilot Plant
ORNL-1938: (1.3M PDF)
The effects of reactor irradiation on thorium-uranium alloy fuel plates
ORNL-1869: (1.3M PDF)
Formation of U²³² and the Effects of its Decay Chain Activity on U-233, Thorium, and the Thorex Process
ORNL-1818: (6.6M PDF)
Products produced in batch neutron irradiation of thorium
ORNL-1817: (11.3M PDF)
Products produced in continuous neutron irradiation of thorium
ORNL-1809: (1.0M PDF)
Properties of thorium oxide ceramics – interim report
ORNL-1757: (1.3M PDF)
Laboratory development of the thorex process: Progress report for August 1, 1953 to June 30, 1954
ORNL-1724: (270K PDF)
Catalog of uranium, thorium, and plutonium isotopes
ORNL-1638: (3.4M PDF)
Project Hope, a chemical reprocessing plant for a nuclear power economy
ORNL-1610: (2.5M PDF)
Laboratory Development of the Thorex Process: progress report, February 1, 1953 to July 31, 1953
ORNL-1558: (1.7M PDF)
A Design and Cost Estimate Study of a Purex Plant
ORNL-1518: (2.0M PDF)
Laboratory development of the Thorex Process: Progress report for October 1, 1952 to January 31, 1953
ORNL-1431: (1.9M PDF)
Laboratory development of the thorex process: progress report, September 30, 1952
ORNL-1425: (1.1M PDF)
Separation of U-233 in the ORNL Pilot Plant
ORNL-1367-Rev: (26.6M PDF)
Process report: Laboratory development of the Thorex Process
ORNL-1367: (26.2M PDF)
Process report: Laboratory development of the Thorex Process
ORNL-1090: (27.1M PDF)
Interim report on metallurgy of thorium and thorium alloys
ORNL-0761: (404K PDF)
Dose rates of radiation from thorium and from enriched uranium
ORNL-TM-5903: (17.4M PDF)
PuO₂ dissolution problem for LWR plutonium recycle and LMFBR fuels: fabrication and reprocessing problems and their resolution
ORNL-TM-5049: (1.7M PDF)
Assessment of the radiological impact of ²³²U and daughters in recycled ²³³U HTGR fuel
ORNL-TM-3469: (2.7M PDF)
Criticality Analysis: Lwbr Assistance Program in Building 3019
ORNL-TM-3422: (5.2M PDF)
Thorium–Uranium Recycle Facility
ORNL-TM-3204: (809K PDF)
Thorium Fuel Cycle Development Progress Report, No. 15, October 1970
ORNL-TM-3194: (1.7M PDF)
Equipment for the Dissolution of Core Material from Sheared Power Reactor Fuels
ORNL-TM-2792: (523K PDF)
Thorium Fuel Cycle Development Progress Report No. 5, December 1969
ORNL-TM-1978: (1.8M PDF)
Engineering development of Sol-Gel Process at the Oak Ridge National Laboratory
ORNL-TM-1784: (7.1M PDF)
Peliminary investigation of processing fast-reactor fuel in an existing plant
ORNL-TM-1501: (1.1M PDF)
Remote Fabrication of Thorium Fuels
ORNL-TM-1144: (3.6M PDF)
Properties of Thorium, its Alloys, and its Compounds
ORNL-TM-1139: (1.6M PDF)
Reprocessing Methods and Costs for Selected Thorium-Bearing Reactor Fuel Types
ORNL-TM-0588: (2.6M PDF)
A new process for the remote preparation and fabrication of fuel elements containing uranium-233 oxide-thorium oxide
ORNL-TM-0543: (4.8M PDF)
Separation of protactinium from thorium in nitric acid solutions by solvent extraction with tributyl phosphate or by adsorption on pulverized unfired VYCOR glass or silica gel
ORNL-TM-0420: (2.4M PDF)
Aqueous Processing of Thorium Fuels, Part III
ORNL-TM-0241: (2.7M PDF)
Thorium Utilization Program: A Survey of Processing Methods for Thorium Reactor Fuels
The Homogeneous Reactor Program, and the Wartime Pile Studies Behind It
Oak Ridge Homogeneous Reactor Program
ORNL-3167: (14.2M PDF)
Calculation of the pulse-height response of NaI(Tl) scintillation counters
ORNL-3061: (8.3M PDF)
Homogeneous Reactor Program Progress Report for Period from August 1 to November 30, 1960
ORNL-3004: (4.1M PDF)
Homogeneous Reactor Program quarterly progress report for period ending July 31, 1960
ORNL-2947: (21.7M PDF)
Homogeneous Reactor Program quarterly progress report for period ending April 30, 1960
ORNL-2920: (19.4M PDF)
Homogeneous Reactor Program quarterly progress report for period ending January 31, 1960
ORNL-2879: (8.6M PDF)
Homogeneous Reactor Program progress report for period May 1 through October 31, 1969
ORNL-2784: (9.7M PDF)
Design of chemical processing plant for homogeneous reactor test
ORNL-2743: (8.2M PDF)
Homogeneous Reactor Project quarterly progress report for period ending April 30, 1959
ORNL-2735: (10.7M PDF)
Corrosion studies for the HRT chemical processing plant
ORNL-2696: (6.0M PDF)
Homogeneous Reactor Project quarterly progress report for period ending January 31, 1959
ORNL-2561: (13.2M PDF)
Homogeneous Reactor Project quarterly progress report for period ending April 30 and July 31, 1958
ORNL-2509: (776K PDF)
Preparation of ThO₂ for homogeneous reactor blanket use
ORNL-2493: (7.9M PDF)
Homogeneous Reactor Project quarterly progress report for period ending January 31, 1958
ORNL-2432: (7.1M PDF)
Homogeneous Reactor Project quarterly progress report for period ending October 31, 1957
ORNL-2379: (5.7M PDF)
Homogeneous Reactor Project quarterly progress report for period ending July 31, 1957
ORNL-2331: (8.8M PDF)
Homogeneous Reactor Project quarterly progress report for period ending April 30, 1957
ORNL-2313: (917K PDF)
Fuel costs in spherical slurry reactors
ORNL-2272: (8.6M PDF)
Homogeneous Reactor Project quarterly Progress report for period ending January 31, 1957
ORNL-2222: (8.7M PDF)
Homogeneous Reactor Project quarterly progress report for period ending October 31, 1956
ORNL-2165: (6.2M PDF)
Some economic and nuclear characteristics of cylindrical thorium breeder reactors
ORNL-2148: (6.7M PDF)
Homogeneous Reactor Project quarterly progress report for period ending July 31, 1956
ORNL-2089: (4.2M PDF)
HRT Reactor hazards
ORNL-2088: (4.9M PDF)
Operational safety of the homogeneous reactor test
ORNL-2072: (6.1M PDF)
Dynamics of the homogeneous reactor test
ORNL-2057: (5.9M PDF)
Homogeneous Reactor Project quarterly progress report for period ending January 31, 1956
ORNL-2004: (7.9M PDF)
Homogeneous Reactor Project quarterly progress report for period ending October 31, 1955
ORNL-1943: (10.1M PDF)
Homogeneous Reactor Project quarterly progress report for period ending July 31, 1955
ORNL-1943: (8.8M PDF)
Homogeneous Reactor Project quarterly progress report for period ending July 31, 1955
ORNL-1904: (1.7M PDF)
Aqueous uranium slurry studies
ORNL-1895: (7.4M PDF)
Homogeneous Reactor Project quarterly progress report for period ending April 30, 1955
ORNL-1858: (14.6M PDF)
Low-power criticality experiments on the homogeneous reactor experiment (HRE-1)
ORNL-1853: (8.2M PDF)
Homogeneous Reactor Project quarterly progress report for period ending January 31, 1955
ORNL-1839: (5.9M PDF)
Decontamination of the Homogeneous Reactor Experiment
ORNL-1813: (6.2M PDF)
Homogeneous Reactor Project quarterly progress report for period ending October 31, 1954
ORNL-1780: (4.5M PDF)
Physics of the Homogeneous Reactor Test – Statics
ORNL-1772: (17.8M PDF)
Homogeneous Reactor Project quarterly progress report for period ending July 31, 1954
ORNL-1753: (21.7M PDF)
Homogeneous Reactor Project quarterly progress report for period ending April 30, 1954
ORNL-1678: (3.3M PDF)
Homogeneous Reactor Project quarterly progress report for period ending January 31, 1954
ORNL-1658: (4.5M PDF)
Homogeneous Reactor Project quarterly progress report for period ending October 31, 1953
ORNL-1605: (4.9M PDF)
Homogeneous Reactor Project quarterly progress report for period ending July 31, 1953
ORNL-1554: (3.9M PDF)
Homogeneous Reactor Project quarterly progress report for period ending March 31, 1953
ORNL-1534: (41.2M PDF)
HRE design manual
ORNL-1478: (3.2M PDF)
Homogeneous Reactor Project quarterly progress report for period ending January 1, 1953
ORNL-1448: (846K PDF)
Prediction of Criticality Behavior of a Slurry upon Settling
ORNL-1424: (3.9M PDF)
Homogeneous reactor project quarterly progress report for period ending October 1, 1952
ORNL-1318: (4.8M PDF)
Homogeneous Reactor Project quarterly progress report for period ending July 1, 1952
ORNL-1280: (6.1M PDF)
Homogeneous Reactor Project quarterly progress report for period ending March 15, 1952
ORNL-1221: (32.7M PDF)
Homogeneous Reactor Project Quarterly Progress Report for Period Ending November 15, 1951
ORNL-1121: (24.0M PDF)
Homogeneous Reactor Project quarterly progress report for period ending August 15, 1951
ORNL-1057: (54.0M PDF)
Homogeneous Reactor Project quarterly progress report for period ending May 15, 1951
ORNL-0826: (4.6M PDF)
Homogeneous Reactor Experiment quarterly progress report for period ending August 31, 1950
ORNL-0794: (1.5M PDF)
Mixing in the core of the HRE
ORNL-0731: (2.7M PDF)
A report on the safety aspects of the homogeneous reactor experiment
ORNL-0630: (4.3M PDF)
Homogeneous Reactor Experiment report for the quarter ending February 28, 1950
ORNL-0517: (404K PDF)
Recent classified nuclear data (declassified August 1970)
ORNL-TM-0348: (155.0M PDF)
HRE-2 design report
ORNL-MIT-132: (1.2M PDF)
Energy Expenditures Associated with the Production and Recycle of Metals
Metallurgical Laboratory and Clinton Laboratories, 1943–1948
CC-822: (659K PDF)
Chemical Research: The Present Status of P-9 Specifications, Purity and Danger Coefficients
CE-805: (6.9M PDF)
General Engineering Design Features of the Pile for a Light Water Cooled P-9 Power Plant
CE-865: (1.5M PDF)
The Results of a Trip to a Heat Exchanger Manufacturers
CE-1074: (1.3M PDF)
Thermal Syphon in Homogeneous Pile
CE-1125: (5.1M PDF)
Shielding of Heterogeneous P-9 Pile
CE-1151: (1.1M PDF)
Terminal Report of P-9 Studies Section
CL-574(5): (249K PDF)
Pile Theory Lecture Notes: May 13, 1943
CL-574(7): (254K PDF)
Pile Theory Lecture Notes: May 25, 1943
CL-574(2): (260K PDF)
Pile Theory Lecture Notes: April 20, 1943
CL-574: (363K PDF)
Pile Theory Lecture Notes: April 13 and 15, 1943
CL-574(12): (416K PDF)
Pile Theory Lecture Notes: June 17, 1943
CL-574(14): (275K PDF)
Pile Theory Lecture Notes: June 22, 1943
CL-574(4): (400K PDF)
Pile Theory Lecture Notes: May 11, 1943
CL-574(13): (297K PDF)
Pile Theory Lecture Notes: June 17, 1943
CP-333: (343K PDF)
Summary– Nutron Cross-Sections of the Elements
CP-779: (488K PDF)
Removal of Power from the Homogeneous Plant
CP-1300: (3.7M PDF)
Physics of the Clinton Pile
CP-2459: (2.5M PDF)
A Brief General Description of the Argonne Uranium-Graphite Pile (CP-2)
CT-900: (1.1M PDF)
Technological Research – P-9 Pile Studies Section
CT-911: (1.4M PDF)
Technological Research – P-9 Pile Studies Section: Slurry Pumps
CT-962: (1.2M PDF)
Technological Research: P-9 Studies Section: Report for Month Ending September 26, 1943
Mon-N-127: (6.8M PDF)
Isolation of U-233 from Thorium and its Compounds
Mon-P-93: (1.1M PDF)
High Pressure Water as a Heat Transfer Medium in Nuclear Power Plants
Mon-P-187: (1.6M PDF)
Methods Available for Calculating Critical Sizes of Slow and Resonance Energy Chain Reacting Systems
Mon-P-190: (2.1M PDF)
Some Notes on Power Piles
Mon-P-198: (2.5M PDF)
Critical Size and Breeding Gain of Resonance Piles
Mon-P-246: (2.3M PDF)
Outline of a Liquid Metal Pile
MUC-EPW-134: (3.3M PDF)
Preliminary Calculations on a Breeder with Circulating Uranium
MUC-EPW-143: (309K PDF)
Memorandum: Plutonium Absorption at Thermal Energies
MUC-FD-8: (2.0M PDF)
Suggestions for a High Temperature Pebble Pile
MUC-FD-8: (1.6M PDF)
Suggestions for a High-Temperature Pebble Pile
MUC-FF-169: (461K PDF)
Importance of 24 for Thermal Breeders
MUC-FLF-5: (4.2M PDF)
Preliminary Report on Critical Sizes and Wall Losses for Breeders and Converters: P-9 Systems
MUC-KW-18: (144K PDF)
Values of Uranium and Plutonium Constants: “Constants Meeting”
MUC-LAO-17: (597K PDF)
Notes on Meeting of April 26, 1944
MUC-LAO-18: (849K PDF)
Notes on Meeting of April 28, 1944
MUC-LAO-19: (594K PDF)
Notes on Meeting of May 5, 1944
MUC-LAO-30: (504K PDF)
Notes on Meeting of July 6, 1944
MUC-LAO-40: (632K PDF)
Notes on Meeting of Wednesday, July 14, 1944
MUC-LAO-41: (444K PDF)
Notes on Meeting of Wednesday, July 26, 1944
MUC-LAO-42: (533K PDF)
Notes on Meeting of Friday, July 28, 1944
MUC-MB-234: (966K PDF)
Reports on Special Topics Developed by Section C-II
MUC-SKA-811: (1.3M PDF)
Piles of the Future Review: Dr. Tolman’s Committee: October 9, 10, 11, 1944
MUC-SKA-811: (760K PDF)
Piles of the Future Review: Dr. Tolman’s Committee: October 9, 10, 11, 1944
N-985: (912K PDF)
Peripheral Production in X Pile
N-2292: (15.9M PDF)
Principles of Nuclear Power: Chapter 22: Control
TID-1117: (1.8M PDF)
Description of Accompanying Preliminary Design Drawings for a Converter Pile Producing 23 and Utilizing 49
Topical Compilations from the MSRP Progress Reports
MSRP Compilation: (18.9M PDF), (116K Analysis)
MSRE Design and Construction Sections, ORNL-3014 through ORNL-3708 (1960–1964)
MSRP Compilation: (8.1M PDF), (153K Analysis)
Graphite-to-Metal Brazing Sections, ORNL-2723 through ORNL-4396 (1959–1969)
MSRP Compilation: (1.0M PDF), (186K Analysis)
Molybdenum Chemistry Sections, ORNL-3215 through ORNL-4782 (1961–1972)
MSRP Compilation: (1.4M PDF), (155K Analysis)
Flowsheet Sections, ORNL-4254 through ORNL-4832 (1968–1972)
MSRP Compilation: (15.6M PDF), (117K Analysis)
MSRE Operations Sections, ORNL-3812 through ORNL-4728 (1965–1971)
MSRP Compilation: (46.1M PDF), (639K Analysis)
Chemistry Sections, ORNL-2684 through ORNL/TM-6415 (1959–1979)
MSRP Compilation: (24.3M PDF), (130K Fluorination Analysis), (104K Distillation Analysis), (124K Reductive Extraction Analysis), (118K Salt Preparation Analysis)
Fuel Processing Sections, ORNL-2684 through ORNL/TM-6415 (1959–1979)
MSRP Compilation: (63.8M PDF)
Hastelloy N (INOR-8) Sections, Volume I, ORNL-2684 through ORNL-4622 (1959–1970)
MSRP Compilation: (48.4M PDF)
Hastelloy N (INOR-8) Sections, Volume II, ORNL-4676 through ORNL-4832 (1971–1972)
MSRP Compilation: (74.1M PDF)
Hastelloy N (INOR-8) Sections, Volume III, ORNL-5011 through ORNL/TM-6415 (1974–1979)
MSRP Compilation: (19.3M PDF)
Graphite Sections, ORNL-2684 through ORNL/TM-6415 (1959–1979)
MSRP Compilation: (8.3M PDF), (449K Analysis)
Pump Development Sections, ORNL-2684 through ORNL-5132 (1959–1976)
MSRP Compilation: (3.5M PDF), (185K Analysis)
Reactor Analysis Sections, ORNL-3014 through ORNL-4548 (1960–1970)
MSRP Compilation: (30.6M PDF), (14.0M Analysis)
MSBR Design and Processing, ORNL-2684 through ORNL/TM-6415 (1959–1979)
MSRP Compilation: (18.4M PDF), (344K Analysis)
Power Conversion Sections, ORNL-2378 through ORNL-5132 (1957–1976)
Nuclear Science and Engineering, 2 2 (February 1957).
Molten Fluorides as Power Reactor Fuels (115K OCR)
The Aircraft Reactor Experiment–Design and Construction (1.3M OCR)
The Aircraft Reactor Experiment–Physics (720K OCR)
The Aircraft Reactor Experiment–Operation (224K OCR)
Fluid Fuel Reactors, Addison-Wesley, 1958.
Part I: Aqueous Homogeneous Reactors
Chapter 1: Homogeneous Reactors and their Development
Chapter 2: Nuclear Characteristics of One- and Two-Region Homogeneous Reactors
Chapter 3: Properties of Aqueous Fuel Solutions
Chapter 4: Technology of Aqueous Suspensions
Chapter 5: Integrity of Metals in Homogeneous Reactor Media
Chapter 6: Chemical Processing
Chapter 7: Design and Construction of Experimental Homogeneous Reactors
Chapter 8: Component Development
Chapter 9: Large-Scale Homogeneous Reactor Studies
Chapter 10: Homogeneous Reactor Cost Studies
Part II: Molten-Salt Reactors
Chapter 11: Introduction
Chapter 12: Chemical Aspects of Molten Fluoride Salt Reactor Fuels
Chapter 13: Construction Materials for Molten-Salt Reactors
Chapter 14: Nuclear Aspects of Molten-Salt Reactors
Chapter 15: Equipment for Molten-Salt Reactors Heat-Transfer Systems
Chapter 16: Aircraft Reactor Experiment
Chapter 17: Conceptual Design of a Power Reactor
Part III: Liquid Metal Fuel Reactors
Chapter 18: Liquid Metal Fuel Reactors
Chapter 19: Reactor Physics for Liquid Metal Reactors Design
Chapter 20: Composition and Properties of Liquid Metal Fuels
Chapter 21: Materials of Construction–Metallurgy
Chapter 22: Chemical Processing
Chapter 23: Engineering Design
Chapter 24: Liquid-Metal Fuel Reactor Design Study
Chapter 25: Additional Liquid Metal Reactors
Nuclear Applications and Technology, 8 2 (February 1970).
Preface: Molten Salt Reactors
Molten-Salt Reactors–History, Status, and Potential
Experience with the Molten-Salt Reactor Experiment
Molten-Salt Reactor Chemistry
New Developments in Materials for Molten-Salt Reactors
Engineering Development of the MSBR Fuel Recycle
Graphite and Xenon Behavior and Their Influence on Molten-Salt Reactor Design
The Design And Performance Features Of A Single-Fluid Molten-Salt Breeder Reactor
Reactor Physics and Fuel Cycle Analyses
Nuclear Applications and Technology, 10 2 (February 1971).
Experiences with Dynamic Testing Methods at the MSRE
Theoretical Dynamics Analysis of the MSRE
Densities of Molten Elements and Representative Salts
Table of Isotopic Masses and Natural Abundances
MSRP status resume 1958
Weinberg MSR correspondence