Fluid Fluorides and Chlorides Reactor Research and Development on
Molten Salt Reactors (MSRs) Papers, Books, and Reports
Dedication:
This site is dedicated to Dr. Uri Gat, who introduced me to Molten Salt Reactors in 1993 and Dr. Ralph Moir, who continues to help and encourage me and many other pilgrims, in our "Molten Salt Adventures" journey.
Last, but definitely not least, I owe a huge debt to the ORNL "Old Boys", as Professor Furukawa used to call the amazing group of ORNL Molten Salt researchers.
As you progress along your own Molten Salt Adventure, one question the technical documents below will not answer is the natural,
"Why was the MSR not pursued?"
I have written a 4 page document to answer that question:
"Why the Molten Salt Reactor (MSR) was not developed by the USA", by Bruce Hoglund, November 2010.
Books
"Fluid Fuel Reactors", 979 pages, Addison-Wesley, 1958.
Journals
MOSELs Design (OCRed 3.5 MB PDF)
Design Concepts for the Core Structure of A Mosel (Molten Salt Experimental) Reactor, 26 June 1965, by P.R. Kasten, U. Gat, S. Schulze Horn, and H.W. Vornhusen, NUCLEAR STRUCTURAL ENGINEERING 2 (1965) 224-232. NORTH-HOLLAND PUBLISHING COMP. AMSTERDAM
NOTE: An Optical Character Recognition (OCR) version of the paper. WARNING: may contain errors!
MOSELs Design (no OCR, 300 dpi image, 6.5 MB PDF)
Design Concepts for the Core Structure of A Mosel (Molten Salt Experimental) Reactor, 26 June 1965, by P.R. Kasten, U. Gat, S. Schulze Horn, and H.W. Vornhusen, NUCLEAR STRUCTURAL ENGINEERING 2 (1965) 224-232. NORTH-HOLLAND PUBLISHING COMP. AMSTERDAM
The MOSEL reactor concept (OCRed 1.5 MB PDF)
Design Concepts for the Core Structure of A Mosel (Molten Salt Experimental) Reactor, 1964, by Paul Kasten, Third International Conference on the Peaceful Uses of Atomic Energy, Geneva 1964, A Conf. 28/P/538 Pf538 Federal Republic of Germany
NOTE: An Optical Character Recognition (OCR) version of the paper. WARNING: may contain errors!
The MOSEL reactor concept (no OCR, 300 dpi image, 10.8 MB PDF)
Design Concepts for the Core Structure of A Mosel (Molten Salt Experimental) Reactor, 1964, by Paul Kasten, Third International Conference on the Peaceful Uses of Atomic Energy, Geneva 1964, A Conf. 28/P/538 Pf538 Federal Republic of Germany
MOSEL cooling concepts (OCRed 2.9 MB PDF)
Cooling Concepts for a Compact MOSEL (Molten Salt) Reactor, by U. Gat, NUCLEAR ENGINEERING AND DESIGN 5 (1967) 113-122. NORTH-HOLLAND PUBLISHING COMP., AMSTERDAM
NOTE: An Optical Character Recognition (OCR) version of the paper. WARNING: may contain errors!
MOSEL cooling concepts (no OCR, 300 dpi image, 9.5 MB PDF)
Cooling Concepts for a Compact MOSEL (Molten Salt) Reactor, by U. Gat, NUCLEAR ENGINEERING AND DESIGN 5 (1967) 113-122. NORTH-HOLLAND PUBLISHING COMP., AMSTERDAM
ORNL Reports Related to Fluid Fluoride Reactors (FFRs) and Technology
ORNL-TM-1060: 1965-09 (19.2 MB PDF)
Molten-Salt Converter Reactor: Design Study and Power Cost Estimates for a 1000 MWe Station, by L.G. Alexander, W.L. Carter, C.W. Craven, D.B. Janney, T.W. Kerlin, and R. Van Winkle
ORNL-2095: 1956-05 (18.9 MB PDF)
Design Report on the Aircraft Reactor Test, by A.P. Fraas and A.W. Savolainen
ORNL-2751: 1959-09 (6 MB PDF)
Nuclear Characteristics of Spherical Homogenous, Two-Region, Molten-Fluoride-Salt Reactors, by L.G. Alexander, D.A. Carrison, H.G. MacPherson, and J.T. Roberts
ORNL-TM-2256: 1968-06-20 (2.0 MB PDF)
Chemical Feasibility of Fueling Molten-Salt Reactors with PuF3, by R.E. Thoma
ORNL-4832: 1973-03 (36.8 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1972
ORNL-4865: 1975-10 (12.8 MB PDF)
Fission Product Behavior in the MSRE, by E.L. Compere, S.S. Kirslis, E.G. Bohlmann, F.F. Blankenship, and W.R. Grimes
ORNL-4874: 1972-12 (13.9 MB PDF)
Development and Construction of a Molybdenum Test Stand, by J.R. DiStefano, A.J. Moorhead, N.C. Cole, and R.E. McDonald
ORNL-4995: 1975-07 (18.1 MB PDF)
An Assessment of Industrial Energy Options Based on Coal and Nuclear Systems, by T.D. Anderson, H.I. Bowers, R.H. Bryan, J.G. Delene, E.C. Hise, J.E. Jones, Jr., O.H. Klepper, S.A. Reed, and I. Spiewak
ORNL-5011: 1975-06 (17.9 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1974, by L.E. McNeese
ORNL-5018: 1974-12 (49.6 MB PDF)
Program Plan for the Development of Molten-Salt Breeder Reactors
ORNL-5047: 1975-09 (32.1 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1975, by L.E. McNeese
ORNL-5078: 1976-02 (30.4 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 197, by L.E. McNeese
ORNL-5132: 1976-08 (37.9 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 29, 1976, by L.E. McNeese
ORNL-5176: 1977-02 (4.2 MB PDF)
Engineering Tests of the Metal Transfer Process for Extraction of Rare-Earth Fission Products From a Molten-Salt Breeder Reactor Fuel Salt, by H.C. Savage and J.R. Hightower, Jr.
ORNL-5388: 1978-12 (18.8 MB PDF)
Interim Assessment of the Denatured 233U Fuel Cycle: Feasibility and Nonproliferation Characteristics, by L.S. Abbott, D.E. Bartine, and T.J. Burns
ORNL-6952: 1999-09 (848K PDF)
Uses For Uranium-233: What Should Be Kept for Future Needs?, by C. W. Forsberg
ORNL-4831: 1973-02 (6.5 MB PDF)
Development of the Variable-Gap Technique for Measuring the Thermal Conductivity of Fluoride Salt Mixtures, by J.W. Cooke
ORNL-5119
Gas-Cooled Fast Reactor Program Progress Report for January 1, 1974 through June 30, 1975, by Uri Gat and Paul R. Kasten
ORNL-5294
Gas-Cooled Fast Reactor Program Progress Report for the Period July 1, 1975 through December 31, 1976, by Uri Gat and Paul R. Kasten
ORNL-4830: 1973-01 (9.8 MB PDF)
The ORNL Automated Orbital Pipe Welding Systems, by Peter P. Holz
ORNL-4829: 1972-11 (52.8 MB PDF)
Intergranular Cracking of INOR-8 in the MSRE, by H.E. McCoy and B. McNabb
ORNL-4812: 1972-08 (34.2 MB PDF)
Development Status of Molten-Salt Breeder Reactors
ORNL-4782: 1972-10 (48.1 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 29, 1972, by M.W. Rosenthal, R.B. Briggs, and P.N. Haubenreich
ORNL-4762: 1972
Considerations in the Long Term Management of High-Level Active Wastes
ORNL-4728: 1972-02 (38.2 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1971, by M.W. Rosenthal, R.B. Briggs, and P.N. Haubenreich
ORNL-4676: 1971-08 (57.0 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1971, by M.W. Rosenthal
ORNL-4658: 1971-12 (23.4 MB PDF)
Chemical Aspects of MSRE Operations, by Roy E. Thoma
ORNL-4622: 1971-01 (34.3 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1970, by M.W. Rosenthal, R.B. Briggs, and P.N. Haubenreich
ORNL-4616: 1971-01 (4.6 MB PDF)
Preparation and Handling of Salt Mixtures for the MSRE, by James H. Shaffer
ORNL-4577: 1971-08 (3.7 MB PDF)
Low-Pressure Distillation of a Portion of the Fuel Carrier Salt from the MSRE, by J.R. Hightower, Jr., L.E. McNeese, B.A. Hannaford, and H.D. Cochran, Jr.
ORNL-4575: 1971-06 (4.3 MB PDF)
Corrosion In Polythermal Loop Systems II. A Solid-State Diffusion Mechanism With and Without Liquid Film Effects, by R.B. Evans III, J.W. Koger, and J.H. DeVan
ORNL-4574: 1971-04 (3.6 MB PDF)
Molten-Salt Fluoride Volatility Pilot Plant: Recovery Of Enriched Uranium From Aluminum-Clad Fuel Elements, by W.H. Carr, L.J. King, F.G. Kitts, W.T. McDuffee, and F.W. Miles
ORNL-4548: 1970-08 (57.0 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1970, by M.W. Rosenthal, R.B. Briggs, and P.R. Kasten
ORNL-4541: 1971-06 (13.2 MB PDF)
Conceptual Design Study of a Single-Fluid Molten-Salt Breeder Reactor
ORNL-4528: 1970-08 (6.9 MB PDF)
Two-Fluid Molten-Salt Breeder Reactor Design Study, by R.C. Robertson, R.B. Briggs, O.L. Smith, and E.S. Bettis
ORNL-4449: 1970-02 (33.4 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1969
ORNL-4434: 1971-01 (3.4 MB PDF)
Low-Pressure Distillation of Molten Fluoride Mixtures: Nonradioactive Tests for The MSRE Distillation Experiment, by J.R. Hightower, Jr. and L.E. McNeese
ORNL-4415: 1972-11 (1.2 MB PDF)
Liquid-Vapor Equilibria in LiF-BeF2 and LiF-BeF2-ThF4 Systems, by F.J. Smith, L.M. Ferris, and C.T. Thompson
ORNL-4396: 1969-08 (40.6 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1969
ORNL-4389: 1969-05 (5.5 MB PDF)
Gas Transport in MSRE Moderator Graphite: II. Effects of Impregnation III. Variation of Flow Properties, by R.B. Evans III, J.L. Rutherford, and A.P. Malinauskas
ORNL-4371: 1969-03 (4.9 MB PDF)
Preparation of Enriching Salt 7LiF-233UF4 for Refueling the Molten Salt Reactor, by John M. Chandler and S.E. Bolt
ORNL-4344: 1969-02 (47.0 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1968, by M.W. Rosenthal
ORNL-4257: 1968-07 (2.1 MB PDF)
An EMF Study of LiF-BeF2 Solutions, by B.F. Hitch and C.F. Baes, Jr.
ORNL-4254: 1968-08 (30.2 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 29, 1968, by M.W. Rosenthal, R.B. Briggs, and P.R. Kasten
ORNL-4233: 1968-02 (4.8 MB PDF)
Zero-Power Physics Experiments on the MSRE, by B.E. Prince, S.J. Ball, J.R. Engel, P.N. Haubenreich, and T.W. Kerlin
ORNL-4224: 1968-11 (4.3 MB PDF)
Fluorination of Falling Droplets of Molten Fluoride Salt as a Means of Recovering Uranium and Plutonium
ORNL-4191: 1967-12 (42.1 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1967
ORNL-4148: 1967-09 (3.4 MB PDF)
Gas Transport in MSRE Moderator Graphite I. Review Of Theory And Counterdiffusion Experiments, by A.P. Malinauskas, J.L. Rutherford, and R.B. Evans III
ORNL-4123: 1967-07 (3.7 MB PDF)
MSRE Control Elements: Manufacture, Inspection, Drawings and Specifications, by G.M. Tolson and A. Taboada
ORNL-4119: 1967-07 (21.3 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1967, by M.W. Rosenthal
ORNL-4076: 1967-03 (17.6 MB PDF)
Reactor Chemistry Division: Annual Progress Report for Period Ending December 31, 1966
ORNL-4069: 1967-06 (4.0 MB PDF)
Development of a Model for Computing 135Xe Migration in the MSRE, by R.J. Kedl and A. Houtzeel
ORNL-4037: 1967-01 (34.1 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1966
ORNL-3996: 1966-08 (10.5 MB PDF)
Design Studies of 1000 MWe Molten-Salt Breeder Reactors
ORNL-3936: 1966-06 (33.2 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1966
ORNL-3913: 1966-03 (17.1 MB PDF)
Reactor Chemistry Division: Annual Progress Report for Period Ending December 31, 1965
ORNL-3872:
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1965
ORNL-3812:
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1965
ORNL-3791: 1966-01 (9.4 MB PDF)
Preliminary Design Study of a Continuous Fluorination-Vacuum Distillation System for an MSBR, by Paul R. Kasten, E.S. Bettis, and Roy C. Robertson
ORNL-3708: 1964-11 (66.3 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending July 31, 1964
ORNL-3626:
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending January 31, 1964
ORNL-3544: 1964-01 (949K PDF)
Reduction of UF6 Retention on Beds of MgF2 Used for Removal of TcF6
ORNL-3529:
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending July 31, 1963
ORNL-3470.pdf: 1963-11 (60.5 MB PDF)
Metals and Ceramics Division Annual Progress Report for Period Ending May 31, 1963
ORNL-3419:
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending January 31, 1963
ORNL-3391: 1963-08 (3.8 MB PDF)
Mixtures of Metals with Molten Salts, by M.A. Bredig
ORNL-3373: 1962-12 (6.3 MB PDF)
Thermal Analysis of Fused Salt Phase Equilibria
ORNL-3369: 1962-12 (24.7 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1962
ORNL-3298:
Recovery of PuF6 by Fluorination of Fused Fluoride Salts
ORNL-3282: 1962-07 (26.2 MB PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1962
ORNL-3215:
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1961
ORNL-3122:
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1961
ORNL-3014: 1960-12 (8.3 MB PDF)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending July 31, 1960
ORNL-2985: 1960-09 (4.7 MB PDF)
The Feasibility of an Unattended Nuclear Power Plant
ORNL-2982:
Self-Diffusion of Chromium in Nickel-Base Alloys
ORNL-2973: 1960-09 (13.1 MB PDF)
Molten-Salt Reactor Program: Quarterly Progress Report for Periods Ending January 31 and April 30, 1960
ORNL-2896: 1960-12 (7.6 MB PDF)
Phase Equilibria in Molten-Salt Breeder Reactor Fuels
ORNL-2890: 1960-03 (10.3 MB PDF)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending October 31, 1959
ORNL-2832: 1961-06 (21.4 MB PDF)
Corrosion Associated with Fluoridation in the ORNL Fluoride Volatility Process
ORNL-2799: 1959-10 (15.5 MB PDF)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending July 31, 1959
ORNL-2796: 1960-03 (3.0 MB PDF)
Experimental Molten-Salt-Fueled 30 MWe Power Reactor
ORNL-2723: 1959-06 (10.9 MB PDF)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending April 30, 1959
ORNL-2684: 1959-03 (13.0 MB PDF)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending January 31, 1959
ORNL-2677: 1959-09 (4.4 MB PDF)
Aluminum Chloride as a Thermodynamic Working Fluid and Heat Transfer Medium
ORNL-2661: 1959-04 (5.0 MB PDF)
The Fused-Salt/Fluoride Volatility Process for Recovering Uranium
ORNL-2658: 1959-04 (5.4 MB PDF)
Measurements Through a Hot Cell Window Using Optical Tooling
ORNL-2634: 1958-12 (20.6 MB PDF)
Molten-Salt Reactor Program Status Report
ORNL-2626: 1959-01 (12.7 MB PDF)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending October 31, 1958
ORNL-2605: 1959-10 (6.6 MB PDF)
Gas-Cooled, Molten-Salt Heat Exchanger Design Study
ORNL-2551:
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending June 30, 1958
ORNL-2295: 1957-06 (6.3 MB PDF)
"Phase Equilibrium Diagrams for Fused Salt Systems", 24 Jun 1957, R.E. Thoma and W.R. Grimes
ORNL-2548: 1959-11 (11.2 MB PDF)
"Phase Diagrams of Nuclear Reactor Materials", 20 Nov 1959, R.E. Thoma, Editor.
ORNL-2474: 1958-05 (21.4 MB PDF)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending January 31, 1958
ORNL-2431:
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending October 31, 1957
ORNL-2387: 1958-02 (53.7 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 30, 1957
ORNL-2378:
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending September 1, 1957
ORNL-2340:
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 30, 1957
ORNL-2338: 1961
Interim Report on Corrosion by Zirconium-Base Fluorides
ORNL-2337: 1959
Interim Report on Corrosion by Alkali-Metal Fluorides: Work to May 1, 1953
ORNL-2278:
Viscosity Measurements on Molten Fluoride Mixtures
ORNL-2274:
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 31, 1957
ORNL-2221:
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 31, 1956
ORNL-2157: 1956-12 (49.5 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1956
ORNL-2106: 1956-09 (37.6 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1956
ORNL-2061:
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1956
ORNL-2048: 1956-03 (5.8 MB PDF)
Corrosion of Materials in Fused Hydroxides
ORNL-2012:
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1955
ORNL-1947: 1955-10 (35.6 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1955
ORNL-1896: 1955-07 (48.7 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1955
ORNL-1868:
Disassembly and Postoperative Examination of the Aircraft Reactor Experiment
ORNL-1864:
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1955
ORNL-1845: 1955-09 (19.9 MB PDF)
Operation of the Aircraft Reactor Experiment
ORNL-1835: 1955-01 (10.5 MB PDF)
Aircraft Reactor Test Hazards Summary Report
ORNL-1816: 1955-01 (43.5 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1954
ORNL-1771: 1954-10 (26.5 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1954
ORNL-1729: 1954-07 (16.8 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1954
ORNL-1721: 1954-05 (10.0 MB PDF)
ORNL Aircraft Nuclear Power Plant Designs
ORNL-1692: 1954-04 (17.4 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1954
ORNL-1649: 1954-01 (25.9 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1953
ORNL-1609: 1953-10 (17.0 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1953
ORNL-1556: 1953-07 (17.9 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1953
ORNL-1515: 1953-04 (38.2 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1953
ORNL-1495: 1953-03 (4.2 MB PDF)
General Information Concerning Hydroxides
ORNL-1491:
Corrosion by Molten Fluorides
ORNL-1490:
General Information Concerning Fluorides
ORNL-1439: 1953-01 (22.0 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1952
ORNL-1375: 1952-11 (18.6 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1952
ORNL-1294: 1952-08 (23.0 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1952
ORNL-1234:
Reactor Program of the Aircraft Nuclear Propulsion Project
ORNL-1227: 1952-05 (30.6 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1952, R. C. Briant
ORNL-1170: 1952-02 (35.4 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1951
ORNL-1154: 1951-12 (23.9 MB 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
ANP-60:
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1951
ORNL-0919:
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1950
ORNL-0858:
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending August 1, 1950
ORNL-0768:
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending May 31, 1950
ORNL-0629:
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending February 28, 1950
ORNL-0528: 1950-01 (3.4 MB PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending November 30, 1949
ORNL-TM-2006-12: 2006-03
Assessment of Candidate Molten-Salt Coolants for the AHTR
ORNL-TM-2006-29: 2006-06
Assessment of Candidate Molten Salt Coolants for the NGNP/NHI Heat-Transfer Loop, D.F. Williams
(Thermochemical Hydrogen production from water; Excellent information about Sodium Fluoroborate and FLiNaK high temperature, 900 C, coolant salts)
ORNL-TM-2213: 1968-11
Design of an Engineering-Scale, Vacuum Distillation Experiment for MSR Fuel, by W.L. Carter, R.B. Lindauer, and L.E. McNeese
ORNL-TM-13553: 1999-06
Disposition Options for Uranium-233
ORNL-TM-13524: 1997-11
Isotopic Dilution Requirements for 233U Criticality Safety in Processing and Disposal Facilities
ORNL-TM-13517: 1998-03
Definition of Weapons-Usable Uranium-233
ORNL-TM-9780-V1: 1986-09
Nuclear Power Options Viability Study--Volume I: Executive Summary
ORNL-TM-9780-V2: 1986-09
Nuclear Power Options Viability Study--Volume II: Reactor Concepts, Descriptions, and Assessments
ORNL-TM-9780-V3: 1986-09
Nuclear Power Options Viability Study--Volume III: Nuclear Discipline Topics
ORNL-TM-9780-V4: 1986-09
Nuclear Power Options Viability Study--Volume IV: Bibliography
ORNL-TM-9756: 1985-09
Extended Storage-in-Place of MSRE Fuel Salt and Flush Salt
ORNL-TM-8298: 1982-12
Thermal-Convection-Loop Study of the Corrosion of Fe-Ni-Cr Alloys by Molten
NaNO3-KNO3
ORNL-TM-7207: 1980-07
Conceptual Design Characteristics of a Denatured Molten-Salt Reactor with Once-Through Fueling
ORNL-TM-6415: 1979-03
Development Status and Potential Program for Development of Proliferation-Resistant Molten-Salt Reactors
ORNL-TM-6413: 1978-08
Molten-Salt Reactors for Efficient Nuclear Fuel Utilization without Plutonium Separation
ORNL-TM-6002: 1977-10
Status of Tellurium-Hastelloy-N Studies in Molten-Fluoride Salts
ORNL-TM-5920: 1978-01
Status of Materials Development for Molten-Salt-Reactors
ORNL-TM-5783: 1977-05
Compatibility Studies of Potential Molten-Salt Breeder Reactor Materials in Molten Fluoride Salts
ORNL-TM-5782: 1977-04
The Corrosion of Type 316 Stainless Steel to Li2BeF4
ORNL-TM-5781: 1977-05
Corrosion of Several Metals in Supercritical Steam at 538 C
ORNL-TM-5759: 1977-04
Distribution and Behavior of Tritium in the Coolant-Salt Technology Facility
ORNL-TM-5682: 1977-01
Survey of Technology for Storage of Thermal Energy in Heat Transfer Salt
ORNL-TM-5540: 1976-11
System Design Description of Forced-Convection Molten-Salt Corrosion Loops MSR-FCL-3 and MSR-FCL-4
ORNL-TM-5503: 1976-11
Temperature Gradient Compatibility Tests of Some Refractory Metals and Alloys in Bi and Bi-Li Solutions
ORNL-TM-5335: 1976-10
Heat Transfer Measurements in a Forced Convection Loop with Two Molten-Fluoride Salts
ORNL-TM-5325: 1976-04
Evaluation of Alternate Secondary (and Tertiary) Coolants for the MSBR
ORNL-TM-5253: 1976-07
Conceptual Design of a Continuous Fluorinator Experimental Facility (CFEF)
ORNL-TM-5104: 1976-03
A Study of Tritium Removal from Fusion Reactor Blankets of Molten-Salt and Lithium-Aluminum
ORNL-TM-4894: 1976-03 (14.5 MB PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 21
ORNL-TM-4870: 1976-01 (12.4 MB PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 20
ORNL-TM-4863: 1975-07 (5.7 MB PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 19
ORNL-TM-4804: 1975-04 (2.3 MB PDF)
A Method for Calculating the Steady-State Distribution of Tritium in an MSBR Plant
ORNL-TM-4802: 1975-06 (2.3 MB PDF)
The Molten-Salt Reactor Information System
ORNL-TM-4698: 1975-03 (4.7 MB PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 18
ORNL-TM-4286: 1972-12 (12.3 MB PDF)
Alloy Compatibility with LiF-BeF2 Salts Containing ThF4 and UF4
ORNL-TM-4272: 1972-12 (13.4 MB PDF)
Compatibility of Brazing Alloys and the Molten Salt NaBF4-NaF at 610 C
ORNL-TM-4271: 1972-12 (6.7 MB PDF)
Mass Transfer Between Hastelloy-N and a Molten NaBF4 Mixture in a Thermal Convection Loop
ORNL-TM-4221: 1972-12 (2.3 MB PDF)
A Forced-Circulation Loop for Corrosion Studies: Hastelloy-N Compatibility with NaBF4-NaF
ORNL-TM-4210: 1976-09 (2.3 MB PDF)
MRPP - Multi-Region Processing Plant Code
ORNL-TM-4189: 1972-12 (12.1 MB PDF)
Evaluation of Hastelloy-N Alloys After Nine Years Exposure to Both a Molten Fluoride Salt and Air
ORNL-TM-4188: 1972-12 (3.5 MB PDF)
Effect of FeF2 Addition on Mass Transfer in a Hastelloy-N/LiF-BeF2-UF4 Thermal Convection Loop System
ORNL-TM-4179: 1973-05 (1.7 MB PDF)
Improved Representation of Some Aspects of Circulating-Fuel Reactor Kinetics
ORNL-TM-4174: 1972-12 (33.3 MB PDF)
Post-Irradiation Examination of Materials from the MSRE
ORNL-TM-4172: 1972-12 (2.3 MB PDF)
Corrosion of Type 304L Stainless Steel and Hastelloy-N by Mixtures of BF3, Air, and Argon
ORNL-TM-4122: 1972-12 (1.5 MB PDF)
Development of a Venturi-Type Bubble Generator for Use in the MSR Xenon Removal System
ORNL-TM-4079: 1973-03 (4.0 MB PDF)
Forced-Convection Heat-Transfer Measurements with a Molten Fluoride Mixture Flowing in a Smooth Tube
ORNL-TM-4056: 1972-12 (1.5 MB PDF)
The Equilibrium of Dilute UF3 Solutions Contained in Graphite
ORNL-TM-4047: 1972-12 (1.7 MB PDF)
Molten Salts as Blanket Fluids in Controlled Fusion Reactors
ORNL-TM-3964: 1972
Neutron-Induced Transmutation of High-Level Radioactive Waste
ORNL-TM-3963: 1972-12 (2.7 MB PDF)
Zero Power Experiments with 233U in the MSRE
ORNL-TM-3939: 1972-12 (4.7 MB PDF)
MSR Component Replacements Using Remote Cutting and Welding Techniques
ORNL-TM-3884: 1972-12 (5.3 MB PDF)
The Migration of a Class of Fission Products (Noble Metals) in the MSRE
ORNL-TM-3866: 1972-10 (13.4 MB PDF)
Corrosion and Mass Transfer Characteristics of NaBF4-NaF in Hastelloy-N
ORNL-TM-3863: 1973-01 (6.2 MB PDF)
Design and Operation of a Forced-Circulation Corrosion Test Facility Employing Hastelloy-N and NaBF4 Salt
ORNL-TM-3832: 1972-06 (4.2 MB PDF)
Design Studies of a Molten-Salt Reactor Demonstration Plant
ORNL-TM-3777: 1972-12 (1.7 MB PDF)
Heat Transfer Salt for High-Temperature Steam Generation
ORNL-TM-3767: 1972-05-05 (2.5 MB PDF)
Hybrid Computer Simulation of the MSBR
ORNL-TM-3763: 1972-04 (0.8 MB PDF)
Estimated Behavior of Titanium in MSBR Chemical Processing Systems
ORNL-TM-3718: 1972-04 (6.5 MB PDF)
Mass Transfer Between Small Bubbles and Liquids in Cocurrent Turbulent Pipeline Flow
ORNL-TM-3609: 1971-12 (2.0 MB PDF)
A Study of the Adherence of Tungsten and Molybdenum Coatings
ORNL-TM-3595: 1971-12 (15.0 MB PDF)
Indexed Abstracts of Selected References on Molten-Salt Reactor Technology
ORNL-TM-3579: 1972-05 (4.9 MB PDF)
Design and Cost Study of a Fluorination-Reductive Extraction-Metal Transfer Processing Plant for the MSBR
ORNL-TM-3563: 1971-11 (1.4 MB PDF)
Availability of Natural Resources for Molten-Salt Breeder Reactors
ORNL-TM-3561: 1971-09 (0.9 MB PDF)
Remote Inspection of Welded Joints
ORNL-TM-3528: 1971-08 (1.7 MB PDF)
Solution of the Equation Describing the Interface Between Two Fluids for Volume and Pressure Between Drops
ORNL-TM-3524: 1971-10 (9.2 MB PDF)
Operation of the Sampler-Enricher in the MSRE
ORNL-TM-3488: 1971-10 (3.5 MB PDF)
Mass Transfer Between Hastelloy-N and Haynes Alloy No. 25 in a Molten Sodium Fluoroborate Mixture
ORNL-TM-3464: 1971-10 (5.2 MB PDF)
Xenon Behavior in the MSRE
ORNL-TM-3428: 1971-07 (1.3 MB PDF)
Estimated Cost of Adding a Third Salt-Circulation Loop for Controlling Tritium Migration in the 1000-MWe MSBR
ORNL-TM-3352: 1972-12 (11.8 MB PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 10
ORNL-TM-3344: 1972-09 (8.8 MB PDF)
Experience with Sodium Fluoroborate Circulation in an MSRE-Scale Facility
ORNL-TM-3321: 1971-07 (3.6 MB PDF)
Thermal Stability of Titanium-Modified Hastelloy-N at 650 and 760 C
ORNL-TM-3303: 1971-08 (1.5 MB PDF)
Further Discussion of Instrumentation and Controls Development Needed for the MSBR
ORNL-TM-3259:
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 9
ORNL-TM-3258:
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 8
ORNL-TM-3257:
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 7
ORNL-TM-3253: 1971-02 (2.1 MB PDF)
MSRE Procedures for the Period Between Examination and Ultimate Disposal
ORNL-TM-3229: 1970-11 (2.6 MB PDF)
Fluid Dynamic Studies of the MSRE Core
ORNL-TM-3177: 1970-11 (2.9 MB PDF)
Molten-Salt Breeder Experiment Design Bases
ORNL-TM-3151: 1972-08 (8.9 MB PDF)
A Study of Fission Products in the Molten-Salt Reactor Experiment by Gamma Spectrometry
ORNL-TM-3145: 1971-03 (6.2 MB PDF)
Thermal Radiation Transfer of Afterheat in MSBR Heat Exchangers
ORNL-TM-3144: 1970-09 (2.3 MB PDF)
Fluorine Production and Recombination in Frozen MSR Salts after Reactor Operation
ORNL-TM-3141: 1971-12 (12.7 MB PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 6
ORNL-TM-3140: 1971-10 (8.9 PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 5
ORNL-TM-3139: 1971-08 (20.9 PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 4
ORNL-TM-3138: 1971-05 (10.8 PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 3
ORNL-TM-3137: 1971-02 (17.2 PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 2
ORNL-TM-3102: 1971-05 (1.2 MB PDF)
MSBR Control Studies: Analog Simulation Program
ORNL-TM-3064: 1971-01 (24.1 MB PDF)
Influence of Ti, Zr, and Hf Additions on the Resistance of Modified Hastelloy-N to Irradiation Damage
ORNL-TM-3063: 1971-03 (11.8 MB PDF)
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens - Fourth Group
ORNL-TM-3053: 1970-11 (10.1 MB PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 1
ORNL-TM-3041: 1973-08 (5.4 MB PDF)
MSRE Operator Training and Operating Techniques
ORNL-TM-3039: 1973-06 (28.7 MB PDF)
MSRE Systems and Components Performance
ORNL-TM-3027: 1970-06 (11.5 MB PDF)
Spray, Mist, Bubbles, and Foam in the MSRE
ORNL-TM-3007: 1970-06 (1.8 MB PDF)
An Extended Hydralic Model of the MSRE Circulating Fuel System
ORNL-TM-3002: 1970-05 (2.3 MB PDF)
Reactor Power Measurement and Heat Transfer Performance in the MSRE
ORNL-TM-2999: 1970-04 (4.2 MB PDF)
Quality-Assurance Practices in Construction and Maintenance of the MSRE
ORNL-TM-2997: 1970-04 (1.2 MB PDF)
Experimental Dynamic Analysis of the MSRE with 233U Fuel
ORNL-TM-2987: 1970-10 (4.6 MB PDF)
Development of Fuel- and Coolant-Salt Centrifugal Pumps for the MSRE
ORNL-TM-2978: 1970-06 (2.3 MB PDF)
Compatibility of Fused Sodium Fluoroborate and BF3 Gas with Hastelloy-N Alloys
ORNL-TM-2974: 1970-04-07 (1.4 MB PDF)
Plans for Post-Operation Examination of the MSRE
ORNL-TM-2970: 1970-05 (1.0 MB PDF)
Calculated Radioactivity of MSRE Fuel Salt
ORNL-TM-2953: 1971-06 (5.3 MB PDF)
A New Approach to a Design of Steam Generators for Molten Salt Reactor Power Plants
ORNL-TM-2952: 1971-11 (3.1 MB PDF)
Parametric Survery of the Effects of Major Parameters of the Design of MSBR Heat Exchangers
ORNL-TM-2927: 1970-05 (2.1 MB PDF)
Control Studies of a 1000-MWe MSBR
ORNL-TM-2858: 1970-04 (4.8 MB PDF)
Tensile Properties of Hastelloy-N Welded After Irradiation
ORNL-TM-2815: 1971-04 (6.3 MB PDF)
Computer Programs for MSBR Heat Exchangers
ORNL-TM-2780: 1969-12 (6.2 MB PDF)
Preliminary Systems Design Description of the Salt Pump Test Stand for the MSBE
ORNL-TM-2743: 1969-12 (4.2 MB PDF)
Design and Construction of Core Irradiation-Specimen Array for MSRE Runs 19 and 20
ORNL-TM-2741: 1970-01 (3.3 MB PDF)
Catastropic Corrosion of Type 304 Stainless Steel in a System Circulating Fused Sodium Fluoroborate
ORNL-TM-2724: 1969-12 (1.2 MB PDF)
Compatibility of Molybdenum-Base Alloy TZM with LiF-BeF2-ThF4-UF4 at 1100 C
ORNL-TM-2712: 1969-11 (7.0 MB PDF)
Feasibility Study of Remote Cutting and Welding for Nuclear Plant Maintenance
ORNL-TM-2685: 1969-08 (0.8 MB PDF)
Inherent Neutron Source in MSRE with Clean 233U Fuel
ORNL-TM-2677: 1969-11 (3.8 MB PDF)
Management of Noble-Gas Fission-Product Wastes from Reprocessing Spent Fuels
ORNL-TM-2647: 1970-01 (15.1 MB PDF)
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens - Third Group
ORNL-TM-2643: 1969-08 (2.6 MB PDF)
Conceptual System Design Description of the Salt Pump Test Stand for the MSBE
ORNL-TM-2596: 1969-07-08
Fractional Crystallization Reactions in the System LiF-BeF2-ThF4
ORNL-TM-2578: 1969-08
Processing of the MSRE Flush and Fuel Salts
ORNL-TM-2571: 1969-07
Theoretical Dynamic Analysis of the MSRE with 233U Fuel
ORNL-TM-2490: 1969-04
Compatibility of Hastelloy-N and Croloy-9M with NaBF4-NaF-KBF4 Fluoroborate Salt
ORNL-TM-2489: 1969-06-02
MSBR Control Studies
ORNL-TM-2486: 1969-03
Extraction of U, Th, and Rare Earths from Molten LiF-BeF2 into Liquid Li-Bi Solutions
ORNL-TM-2478: 1969-03
Design, Construction, and Testing of a Large Molten Salt Filter
ORNL-TM-2405: 1969-01
Dynamic Analysis of a Salt Supercritical Water Heat Exchanger and Throttle used with MSRE
ORNL-TM-2373: 1968-12
Bubbles, Drops, and Entrainment in Molten Salts
ORNL-TM-2359: 1969-02
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens - Second Group
ORNL-TM-2335: 1969-01
Solubility of Cerium Trifluoride in Molten Mixtures of LiF, BeF2, and ThF4
ORNL-TM-2318: 1969-02-06
Determination of the Void Fraction in the MSRE Using Small Induced Pressure Perturbations
ORNL-TM-2316: 1968-08
Physical Properties of Molten-Salt Reactor Fuel, Coolant, and Flush Salts
ORNL-TM-2315: 1968-08-27
Measurement of Helium Void Fraction in the MSRE Fuel Salt using Neutron-Noise Analysis
ORNL-TM-2305: 1968-12
Postirradiation Tensile and Creep-Rupture Properties of Incoloy 800 at 700 and 760 C
ORNL-TM-2304: 1968-09
MSRE Design and Operations Report Part XI-A: Test Program for 233U Operations
ORNL-TM-2282: 1968-07-10
Preliminary Study of a Molten-Salt Burst Reactor
ORNL-TM-2258: 1968-09
Irradiation Behavior of Cladding and Structural Materials
ORNL-TM-2245: 1968-07-23
Removal of 135Xe from Circulating Fuel Salt of the MSBR by Mass Transfer to Helium Bubbles
ORNL-TM-2238: 1968-07
Proton Reaction Analysis for Lithium and Fluorine in Graphite using a Slit-Scanning Technique
ORNL-TM-2213: 1968-11
Design of an Engineering-Scale, Vacuum Distillation Experiment for MSR Fuel
ORNL-TM-2180: 1968-03-26
Electrical Conductivity of Molten Fluorides: A Review
ORNL-TM-2136: 1969-02
Graphite Behavior and its Effects on MSBR Performance
ORNL-TM-2111: 1968-02
MSRE Design and Operations Part Report V-A: Safety Analysis of Operation with 233U
ORNL-TM-2098: 1968-01-03
Tube Vibration in MSRE Primary Heat Exchanger
ORNL-TM-2058: 1968-01
Measurement of Relative Volatilities of Rare-Earth Fluorides in Mixtures of LiF and BeF2
ORNL-TM-2036: 1967-11-02
Reduction of Iron Dissolved in Molten LiF-ThF4
ORNL-TM-2032: 1967-11-01
Closed-Circuit Television Viewing in Maintenance of Radioactive Systems at ORNL
ORNL-TM-2029: 1967-11
Investigation of One Concept of a Thermal Shield for the Room Housing an MSBR
ORNL-TM-1997: 1967-11
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens - First Group
ORNL-TM-1993: 1967-09
Experience with Hi-Temp Centrifugal Pumps and their Application to MSBRs
ORNL-TM-1976: 1967-10
A Literature Survey of the Fluorides and Oxyfluorides of Molybdenum
ORNL-TM-1960: 1967-12
Operation of Molten-Salt Convection Loops in the ORR
ORNL-TM-1946: 1967-08 (4.4 MB PDF)
Review of Molten-Salt Reactor Physics Calculations
ORNL-TM-1859: 1967-06-30
Maintenance Development Program for MSBRs
ORNL-TM-1858: 1967-06-09
Safety Program for MSBRs
ORNL-TM-1857: 1967-06-12
Physics Program for MSBRs
ORNL-TM-1856: 1967-05-22
Instrumentation and Controls Development for MSBRs
ORNL-TM-1854: 1967-06
Materials Development for MSBRs
ORNL-TM-1853: 1967-06-06
Chemical Research and Development for MSBRs
ORNL-TM-1852: 1967-06
Fuel and Blanket Processing Development for MSBRs
ORNL-TM-1851: 1967-06-12
Summary of the Objectives, Design, and a Program of Development of MSBRs
ORNL-TM-1810: 1967-07
A Model for Computing the Migration of Very Short-Lived Noble Gases into MSRE Graphite
ORNL-TM-1796: 1967-03-10
The Reactivity Balance in the MSRE
ORNL-TM-1730: 1967-03
Considerations of Low-Pressure Distillation of MSBR Fuels
ORNL-TM-1647: 1966-10-13
Experimental Dynamic Analysis of the MSRE
ORNL-TM-1626: 1966-10
Period Measurements on the MSRE During Fuel Circulation: Theory and Experiment
ORNL-TM-1623: 1966-09-07
Tests of Various Particle Filters for Removal of Oil Mists and Hydrocarbon Vapor
ORNL-TM-1545: 1967-09
Design Study of a Heat-Exchange System for One MSBR Concept
ORNL-TM-1543: 1966-06-01
Removal of Protactinium from Molten Fluoride Breeder Blanket Mixtures
ORNL-TM-1467: 1966-03-24
Summary of Molten-Salt Breeder Reactor Design Studies
ORNL-TM-1445: 1966-04-05
Simulators for Training MSRE Operators
ORNL-TM-1437: 1966-04
A Study of Lead and Lead-Salt Corrosion in Thermal-Convection Loops
ORNL-TM-1129: 1965-05-07
Oxide Chemistry and Thermodynamics of Molten LiF-BeF2 by Equilibriation with Gaseous H2O-HF Mixtures
ORNL-TM-1070: 1965-12
Stability Analysis of the MSRE
ORNL-TM-1051: 1965-03-11
Reconstitution of MSR Fuel by Reducing UF6 Gas to UF4 in a Molten Salt
ORNL-TM-1023: 1965-02
Tube Plugging in the MSRE Primary Heat Exchanger
ORNL-TM-1017: 1965-02
Tensile and Creep Properties of INOR-8 for the MSRE
ORNL-TM-0935: 1964-09-11
MSRE Neutron Source Requirements
ORNL-TM-0911: 1965-01
MSRE Design and Operations Report Part XI: Test Program
ORNL-TM-0910: 1965-01
MSRE Design and Operations Report Part X: Maintenance Equipment and Procedures
ORNL-TM-0909: 1965-01
MSRE Design and Operations Report Part IX: Safety Procedures and Emergency Plans
ORNL-TM-0907(rev): 1968-12-28
MSRE Design and Operations Report Part VII: Fuel Handling and Processing Plant (revision)
ORNL-TM-0907: 1965-01
MSRE Design and Operations Report Part VII: Fuel Handling and Processing Plant
ORNL-TM-0733(rev 3): 1969-07-25
MSRE Design and Operations Report Part VI: Operating Limits (Revision 3)
ORNL-TM-0733(rev 2): 1966-09-19
MSRE Design and Operations Report Part VI: Operating Limits (Revision 2)
ORNL-TM-0733(rev): 1965-08-03
MSRE Design and Operations Report Part VI: Operating Limits (Revision)
ORNL-TM-0733: 1965-01
MSRE Design and Operations Report Part VI: Operating Limits
ORNL-TM-0732: 1965-01
MSRE Design and Operations Report Part V: Reactor Safety Analysis Report
ORNL-TM-0730: 1965-01
MSRE Design and Operations Report Part III: Nuclear Analysis
ORNL-TM-0729B: 1965-01
MSRE Design and Operations Report Part IIB: Nuclear and Process Instrumentation
ORNL-TM-0729A: 1965-01
MSRE Design and Operations Report Part IIA: Nuclear and Process Instrumentation
ORNL-TM-0728: 1965-01
MSRE Design and Operations Report Part I: Description of Reactor Design
ORNL-TM-0611: 1963-08-27
Inherent Neutron Sources in Clean MSRE Fuel Salt
ORNL-TM-0528: 1963-05-01
Design and Operation of Forced-Circulation Corrosion Testing Loops with Molten Salt
ORNL-TM-0522: 1962-10-10
Design Studies and Cost Estimates of Two Fluoride Volatility Plants
ORNL-TM-0500: 1963-03-13
Radiation Chemistry of MSR System
ORNL-TM-0497: 1966-08-16
Analysis of Filling Accidents in MSRE
ORNL-TM-0458: 1962-12-14
Some Chemical Aspects of Molten-Salt Reactor Safety
ORNL-TM-0380: 1962-10-13
Prediction of Effective Yields of Delayed Neutrons in MSRE
ORNL-TM-0379: 1962-10-15
Temperature and Reactivity Coefficient Averaging in the MSRE
ORNL-TM-0378: 1962-11-05
Temperatures in the MSRE Core During Steady-State Power Operations
ORNL-TM-0328: 1962-09-19
Corrosion Behavior of Reactor Materials in Fluoride Salt Mixtures
ORNL-TM-0251: 1962-05-15
Safety Calculations for MSRE
ORNL-TM-0202: 1969-05
Corrosion Behavior of Nickel-Molybdenum Alloys in Fused Fluoride Mixtures
ORNL-TM-0128: 1962-02-28
Development of Freeze Valve for Use in the MSRE
ORNL-TM-0079: 1962-03-27
Water Test Development of the Fuel Pump for the MSRE
ORNL-TM-0078: 1962-10-03
Thermal-Stress and Strain-Fatigue Analyses of the MSRE Fuel and Coolant Pump Tanks
ORNL-CF-61-8-86: 1961-08-18
Thorium Breeder Reactor Evaluation Part I: Fuel Yields and Cost of a MSBR
ORNL-CF-61-4-62: 1961-04-19
MSRE Preliminary Physics Report
ORNL-CF-60-12-111: 1960-12-13
Homogeneous Molten-Salt Reactors
ORNL-CF-60-11-108: 1960-11-30
MSRE Radiator Design
ORNL-CF-59-12-64: 1960-01-12
Molten-Salt Breeder Reactors
ORNL-CF-59-8-133: 1959-08-31
Molten Salt-Graphite Compatibility Test Results
ORNL-CF-59-2-61: 1959-04-01
Processing of Molten Salt Power Reactor Fuel
ORNL-CF-58-2-46: 1958-02-05
A Molten-Salt Natural Convection Reactor System
ORNL-CF-57-4-92: 1957-04-08
Maintenance of Various Reactor Types
ORNL-CF-53-9-84: 1953-08-14
A Reflector-Moderated, Circulating Fuel Aircraft Reactor
Fluid Chloride Reactors
EIR-411: 1980-07
Reactor with Very Low Fission Product Inventory
EIR-332: 1978-01
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
Transmutation of Fission Products in a Liquid-Fuelled Fast Fission Reactor with Thermal Column
EIR-267: 1974-12
Chemical State of Sulphur Obtained by the
35Cl(n,p)35S Reaction
During In-Pile Irradiation
EIR-259: 1975-09
A High-Flux Fast Molten Salt Reactor for the Transmutation of
137Ce and 90Sr
AEEW-R956: 1974-08
An Assessment of a 2500 MWe Molten Chloride Salt Fast Reactor
EIR-257: 1974-05
The Possibility of Continuous In-core Gaseous Extraction
of Volatile Fission Products in a Molten Fuel Reactor
EIR-249: 1974-01
A Molten Salt Fast Thermal Reactor System with no Waste
ANSE-1-277: 1974
Molten Plutonium Chloride Fast Breeder Reactor Cooled by Molten Uranium Chloride
NED-5-109: 1967
New Boiling Salt Fast Breeder Reactor Concepts
NA-3-540: 1967
Fuel Properties and Nuclear Performance of Fast Reactors Fueled with Molten Chlorides
NSE-23-189: 1965
Fission Product Effects in Molten Chloride Fast-Reactor Fuels
ANL-6792: 1963-10
Molten-Salt Fast Reactors
ORNL-CF-56-8-204: 1956-08
Fused Salt Fast Breeder
MIT-5001: 1952-10-15
Chemical Problems of Non-Aqueous Fluid-Fuel Reactors
MIT-5000: 1952-10-15
Nuclear Problems of Non-Aqueous Fluid-Fuel Reactors
Dr. Eric Ottewitte, INEL: 1992-04
Cursory First Look at the Molten Chloride Fast Reactor as an Alternative
to the Conventional BATR Concept
Dr. Eric Ottewitte, UCLA: 1982
Configuration of a Molten Chloride Fast Reactor on a Thorium Fuel Cycle to Current Nuclear Fuel Cycle Concerns
Other 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
MSR-FUJI: 2004-05-11
MSR-FUJI General Information, Technical Features, and Operating Characteristics
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
ORAU-IEA-77-13: 1977
MSR Concepts with Reduced Potential for Proliferation of Special Nuclear Materials
ORNL-MIT-117: 1970-11-18
Removal of Tritium from the Molten-Salt Breeder Reactor Fuel, M.D. Shapiro and C.M. Reed
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
ORNL-TM-9780-V1: 1986-09
Nuclear Power Options Viability Study--Volume I: Executive Summary
ORNL-TM-9780-V2: 1986-09
Nuclear Power Options Viability Study--Volume II: Reactor Concepts, Descriptions, and Assessments
ORNL-TM-9780-V3: 1986-09
Nuclear Power Options Viability Study--Volume III: Nuclear Discipline Topics
ORNL-TM-9780-V4: 1986-09
Nuclear Power Options Viability Study--Volume IV: Bibliography
ORNL-TM-9756: 1985-09
Extended Storage-in-Place of MSRE Fuel Salt and Flush Salt
ORNL-TM-8298: 1982-12
Thermal-Convection-Loop Study of the Corrosion of Fe-Ni-Cr Alloys by Molten
NaNO3-KNO3
ORNL-TM-7207: 1980-07
Conceptual Design Characteristics of a Denatured Molten-Salt Reactor with Once-Through Fueling
ORNL-TM-6415: 1979-03
Development Status and Potential Program for Development of Proliferation-Resistant Molten-Salt Reactors
ORNL-TM-6413: 1978-08
Molten-Salt Reactors for Efficient Nuclear Fuel Utilization without Plutonium Separation
ORNL-TM-6002: 1977-10
Status of Tellurium-Hastelloy-N Studies in Molten-Fluoride Salts
ORNL-TM-5920: 1978-01
Status of Materials Development for Molten-Salt-Reactors
ORNL-TM-5783: 1977-05
Compatibility Studies of Potential Molten-Salt Breeder Reactor Materials in Molten Fluoride Salts
ORNL-TM-5782: 1977-04
The Corrosion of Type 316 Stainless Steel to Li2BeF4
ORNL-TM-5781: 1977-05
Corrosion of Several Metals in Supercritical Steam at 538 C
ORNL-TM-5759: 1977-04
Distribution and Behavior of Tritium in the Coolant-Salt Technology Facility
ORNL-TM-5682: 1977-01
Survey of Technology for Storage of Thermal Energy in Heat Transfer Salt
ORNL-TM-5540: 1976-11
System Design Description of Forced-Convection Molten-Salt Corrosion Loops MSR-FCL-3 and MSR-FCL-4
ORNL-TM-5503: 1976-11
Temperature Gradient Compatibility Tests of Some Refractory Metals and Alloys in Bi and Bi-Li Solutions
ORNL-TM-5335: 1976-10
Heat Transfer Measurements in a Forced Convection Loop with Two Molten-Fluoride Salts
ORNL-TM-5325: 1976-04
Evaluation of Alternate Secondary (and Tertiary) Coolants for the MSBR
ORNL-TM-5253: 1976-07
Conceptual Design of a Continuous Fluorinator Experimental Facility (CFEF)
ORNL-TM-5104: 1976-03
A Study of Tritium Removal from Fusion Reactor Blankets of Molten-Salt and Lithium-Aluminum
ORNL-TM-4894: 1976-03 (14.5 MB PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 21
ORNL-TM-4870: 1976-01 (12.4 MB PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 20
ORNL-TM-4863: 1975-07 (5.7 MB PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 19
ORNL-TM-4804: 1975-04 (2.3 MB PDF)
A Method for Calculating the Steady-State Distribution of Tritium in an MSBR Plant
ORNL-TM-4802: 1975-06 (2.3 MB PDF)
The Molten-Salt Reactor Information System
ORNL-TM-4698: 1975-03 (4.7 MB PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 18
ORNL-TM-4286: 1972-12 (12.3 MB PDF)
Alloy Compatibility with LiF-BeF2 Salts Containing ThF4 and UF4
ORNL-TM-4272: 1972-12 (13.4 MB PDF)
Compatibility of Brazing Alloys and the Molten Salt NaBF4-NaF at 610 C
ORNL-TM-4271: 1972-12
(6.7 MB PDF)
Mass Transfer Between Hastelloy-N and a Molten NaBF4 Mixture in a Thermal Convection Loop
ORNL-TM-4221: 1972-12
(2.3 MB PDF)
A Forced-Circulation Loop for Corrosion Studies: Hastelloy-N Compatibility with NaBF4-NaF
(2.3 MB PDF)
MRPP - Multi-Region Processing Plant Code
ORNL-TM-4189: 1972-12
ORNL-TM-4210: 1976-09
(12.1 MB PDF)
Evaluation of Hastelloy-N Alloys After Nine Years Exposure to Both a Molten Fluoride Salt and Air
ORNL-TM-4188: 1972-12 (3.5 MB PDF)
Effect of FeF2 Addition on Mass Transfer in a Hastelloy-N/LiF-BeF2-UF4 Thermal Convection Loop System
ORNL-TM-4179: 1973-05 (1.7 MB PDF)
Improved Representation of Some Aspects of Circulating-Fuel Reactor Kinetics
ORNL-TM-4174: 1972-12 (33.3 MB PDF)
Post-Irradiation Examination of Materials from the MSRE
ORNL-TM-4172: 1972-12 (2.3 MB PDF)
Corrosion of Type 304L Stainless Steel and Hastelloy-N by Mixtures of BF3, Air, and Argon
ORNL-TM-4122: 1972-12 (1.5 MB PDF)
Development of a Venturi-Type Bubble Generator for Use in the MSR Xenon Removal System
ORNL-TM-4079: 1973-03 (4.0 MB PDF)
Forced-Convection Heat-Transfer Measurements with a Molten Fluoride Mixture Flowing in a Smooth Tube
ORNL-TM-4056: 1972-12 (1.5 MB PDF)
The Equilibrium of Dilute UF3 Solutions Contained in Graphite
ORNL-TM-4047: 1972-12 (1.7 MB PDF)
Molten Salts as Blanket Fluids in Controlled Fusion Reactors
ORNL-TM-3964: 1972
Neutron-Induced Transmutation of High-Level Radioactive Waste
ORNL-TM-3963: 1972-12 (2.7 MB PDF)
Zero Power Experiments with 233U in the MSRE
ORNL-TM-3939: 1972-12 (4.7 MB PDF)
MSR Component Replacements Using Remote Cutting and Welding Techniques
ORNL-TM-3884: 1972-12 (5.3 MB PDF)
The Migration of a Class of Fission Products (Noble Metals) in the MSRE
ORNL-TM-3866: 1972-10 (13.4 MB PDF)
Corrosion and Mass Transfer Characteristics of NaBF4-NaF in Hastelloy-N
ORNL-TM-3863: 1973-01 (6.2 MB PDF)
Design and Operation of a Forced-Circulation Corrosion Test Facility Employing Hastelloy-N and NaBF4 Salt
ORNL-TM-3832: 1972-06 (4.2 MB PDF)
Design Studies of a Molten-Salt Reactor Demonstration Plant
ORNL-TM-3777: 1972-12 (1.7 MB PDF)
Heat Transfer Salt for High-Temperature Steam Generation
ORNL-TM-3767: 1972-05-05 (2.5 MB PDF)
Hybrid Computer Simulation of the MSBR
ORNL-TM-3763: 1972-04 (0.8 MB PDF)
Estimated Behavior of Titanium in MSBR Chemical Processing Systems
ORNL-TM-3718: 1972-04 (6.5 MB PDF)
Mass Transfer Between Small Bubbles and Liquids in Cocurrent Turbulent Pipeline Flow
ORNL-TM-3609: 1971-12 (2.0 MB PDF)
A Study of the Adherence of Tungsten and Molybdenum Coatings
ORNL-TM-3595: 1971-12 (15.0 MB PDF)
Indexed Abstracts of Selected References on Molten-Salt Reactor Technology
ORNL-TM-3579: 1972-05 (4.9 MB PDF)
Design and Cost Study of a Fluorination-Reductive Extraction-Metal Transfer Processing Plant for the MSBR
ORNL-TM-3563: 1971-11 (1.4 MB PDF)
Availability of Natural Resources for Molten-Salt Breeder Reactors
ORNL-TM-3561: 1971-09 (0.9 MB PDF)
Remote Inspection of Welded Joints
ORNL-TM-3528: 1971-08 (1.7 MB PDF)
Solution of the Equation Describing the Interface Between Two Fluids for Volume and Pressure Between Drops
ORNL-TM-3524: 1971-10 (9.2 MB PDF)
Operation of the Sampler-Enricher in the MSRE
ORNL-TM-3488: 1971-10 (3.5 MB PDF)
Mass Transfer Between Hastelloy-N and Haynes Alloy No. 25 in a Molten Sodium Fluoroborate Mixture
ORNL-TM-3464: 1971-10 (5.2 MB PDF)
Xenon Behavior in the MSRE
ORNL-TM-3428: 1971-07 (1.3 MB PDF)
Estimated Cost of Adding a Third Salt-Circulation Loop for Controlling Tritium Migration in the 1000-MWe MSBR
ORNL-TM-3352: 1972-12 (11.8 MB PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 10
ORNL-TM-3344: 1972-09 (8.8 MB PDF)
Experience with Sodium Fluoroborate Circulation in an MSRE-Scale Facility
ORNL-TM-3321: 1971-07 (3.6 MB PDF)
Thermal Stability of Titanium-Modified Hastelloy-N at 650 and 760 C
ORNL-TM-3303: 1971-08 (1.5 MB PDF)
Further Discussion of Instrumentation and Controls Development Needed for the MSBR
ORNL-TM-3259:
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 9
ORNL-TM-3258:
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 8
ORNL-TM-3257:
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 7
ORNL-TM-3253: 1971-02 (2.1 MB PDF)
MSRE Procedures for the Period Between Examination and Ultimate Disposal
ORNL-TM-3229: 1970-11 (2.6 MB PDF)
Fluid Dynamic Studies of the MSRE Core
ORNL-TM-3177: 1970-11 (2.9 MB PDF)
Molten-Salt Breeder Experiment Design Bases
ORNL-TM-3151: 1972-08 (8.9 MB PDF)
A Study of Fission Products in the Molten-Salt Reactor Experiment by Gamma Spectrometry
ORNL-TM-3145: 1971-03 (6.2 MB PDF)
Thermal Radiation Transfer of Afterheat in MSBR Heat Exchangers
ORNL-TM-3144: 1970-09 (2.3 MB PDF)
Fluorine Production and Recombination in Frozen MSR Salts after Reactor Operation
ORNL-TM-3141: 1971-12 (12.7 MB PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 6
ORNL-TM-3140: 1971-10 (8.9 PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 5
ORNL-TM-3139: 1971-08 (20.9 PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 4
ORNL-TM-3138: 1971-05 (10.8 PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 3
ORNL-TM-3137: 1971-02 (17.2 PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 2
ORNL-TM-3102: 1971-05 (1.2 MB PDF)
MSBR Control Studies: Analog Simulation Program
ORNL-TM-3064: 1971-01 (24.1 MB PDF)
Influence of Ti, Zr, and Hf Additions on the Resistance of Modified Hastelloy-N to Irradiation Damage
ORNL-TM-3063: 1971-03 (11.8 MB PDF)
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens - Fourth Group
ORNL-TM-3053: 1970-11 (10.1 MB PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 1
ORNL-TM-3041: 1973-08 (5.4 MB PDF)
MSRE Operator Training and Operating Techniques
ORNL-TM-3039: 1973-06 (28.7 MB PDF)
MSRE Systems and Components Performance
ORNL-TM-3027: 1970-06 (11.5 MB PDF)
Spray, Mist, Bubbles, and Foam in the MSRE
ORNL-TM-3007: 1970-06 (1.8 MB PDF)
An Extended Hydralic Model of the MSRE Circulating Fuel System
ORNL-TM-3002: 1970-05 (2.3 MB PDF)
Reactor Power Measurement and Heat Transfer Performance in the MSRE
ORNL-TM-2999: 1970-04 (4.2 MB PDF)
Quality-Assurance Practices in Construction and Maintenance of the MSRE
ORNL-TM-2997: 1970-04 (1.2 MB PDF)
Experimental Dynamic Analysis of the MSRE with 233U Fuel
ORNL-TM-2987: 1970-10 (4.6 MB PDF)
Development of Fuel- and Coolant-Salt Centrifugal Pumps for the MSRE
ORNL-TM-2978: 1970-06 (2.3 MB PDF)
Compatibility of Fused Sodium Fluoroborate and BF3 Gas with Hastelloy-N Alloys
ORNL-TM-2974: 1970-04-07 (1.4 MB PDF)
Plans for Post-Operation Examination of the MSRE
ORNL-TM-2970: 1970-05 (1.0 MB PDF)
Calculated Radioactivity of MSRE Fuel Salt
ORNL-TM-2953: 1971-06 (5.3 MB PDF)
A New Approach to a Design of Steam Generators for Molten Salt Reactor Power Plants
ORNL-TM-2952: 1971-11 (3.1 MB PDF)
Parametric Survery of the Effects of Major Parameters of the Design of MSBR Heat Exchangers
ORNL-TM-2927: 1970-05 (2.1 MB PDF)
Control Studies of a 1000-MWe MSBR
ORNL-TM-2858: 1970-04 (4.8 MB PDF)
Tensile Properties of Hastelloy-N Welded After Irradiation
ORNL-TM-2815: 1971-04 (6.3 MB PDF)
Computer Programs for MSBR Heat Exchangers
ORNL-TM-2780: 1969-12 (6.2 MB PDF)
Preliminary Systems Design Description of the Salt Pump Test Stand for the MSBE
ORNL-TM-2743: 1969-12 (4.2 MB PDF)
Design and Construction of Core Irradiation-Specimen Array for MSRE Runs 19 and 20
ORNL-TM-2741: 1970-01 (3.3 MB PDF)
Catastropic Corrosion of Type 304 Stainless Steel in a System Circulating Fused Sodium Fluoroborate
ORNL-TM-2724: 1969-12 (1.2 MB PDF)
Compatibility of Molybdenum-Base Alloy TZM with LiF-BeF2-ThF4-UF4 at 1100 C
ORNL-TM-2712: 1969-11 (7.0 MB PDF)
Feasibility Study of Remote Cutting and Welding for Nuclear Plant Maintenance
ORNL-TM-2685: 1969-08 (0.8 MB PDF)
Inherent Neutron Source in MSRE with Clean 233U Fuel
ORNL-TM-2677: 1969-11 (3.8 MB PDF)
Management of Noble-Gas Fission-Product Wastes from Reprocessing Spent Fuels
ORNL-TM-2647: 1970-01 (15.1 MB PDF)
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens - Third Group
ORNL-TM-2643: 1969-08 (2.6 MB PDF)
Conceptual System Design Description of the Salt Pump Test Stand for the MSBE
ORNL-TM-2596: 1969-07-08
Fractional Crystallization Reactions in the System LiF-BeF2-ThF4
ORNL-TM-2578: 1969-08
Processing of the MSRE Flush and Fuel Salts
ORNL-TM-2571: 1969-07
Theoretical Dynamic Analysis of the MSRE with 233U Fuel
ORNL-TM-2490: 1969-04
Compatibility of Hastelloy-N and Croloy-9M with NaBF4-NaF-KBF4 Fluoroborate Salt
ORNL-TM-2489: 1969-06-02
MSBR Control Studies
ORNL-TM-2486: 1969-03
Extraction of U, Th, and Rare Earths from Molten LiF-BeF2 into Liquid Li-Bi Solutions
ORNL-TM-2478: 1969-03
Design, Construction, and Testing of a Large Molten Salt Filter
ORNL-TM-2405: 1969-01
Dynamic Analysis of a Salt Supercritical Water Heat Exchanger and Throttle used with MSRE
ORNL-TM-2373: 1968-12
Bubbles, Drops, and Entrainment in Molten Salts
ORNL-TM-2359: 1969-02
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens - Second Group
ORNL-TM-2335: 1969-01
Solubility of Cerium Trifluoride in Molten Mixtures of LiF, BeF2, and ThF4
ORNL-TM-2318: 1969-02-06
Determination of the Void Fraction in the MSRE Using Small Induced Pressure Perturbations
ORNL-TM-2316: 1968-08
Physical Properties of Molten-Salt Reactor Fuel, Coolant, and Flush Salts
ORNL-TM-2315: 1968-08-27
Measurement of Helium Void Fraction in the MSRE Fuel Salt using Neutron-Noise Analysis
ORNL-TM-2305: 1968-12
Postirradiation Tensile and Creep-Rupture Properties of Incoloy 800 at 700 and 760 C
ORNL-TM-2304: 1968-09
MSRE Design and Operations Report Part XI-A: Test Program for 233U Operations
ORNL-TM-2282: 1968-07-10
Preliminary Study of a Molten-Salt Burst Reactor
ORNL-TM-2258: 1968-09
Irradiation Behavior of Cladding and Structural Materials
ORNL-TM-2256: 1968-06-20
Chemical Feasibility of Fueling Molten-Salt Reactors with PuF3
ORNL-TM-2245: 1968-07-23
Removal of 135Xe from Circulating Fuel Salt of the MSBR by Mass Transfer to Helium Bubbles
ORNL-TM-2238: 1968-07
Proton Reaction Analysis for Lithium and Fluorine in Graphite using a Slit-Scanning Technique
ORNL-TM-2180: 1968-03-26
Electrical Conductivity of Molten Fluorides: A Review
ORNL-TM-2136: 1969-02
Graphite Behavior and its Effects on MSBR Performance
ORNL-TM-2111: 1968-02
MSRE Design and Operations Part Report V-A: Safety Analysis of Operation with 233U
ORNL-TM-2098: 1968-01-03
Tube Vibration in MSRE Primary Heat Exchanger
ORNL-TM-2058: 1968-01
Measurement of Relative Volatilities of Rare-Earth Fluorides in Mixtures of LiF and BeF2
ORNL-TM-2036: 1967-11-02
Reduction of Iron Dissolved in Molten LiF-ThF4
ORNL-TM-2032: 1967-11-01
Closed-Circuit Television Viewing in Maintenance of Radioactive Systems at ORNL
ORNL-TM-2029: 1967-11
Investigation of One Concept of a Thermal Shield for the Room Housing an MSBR
ORNL-TM-1997: 1967-11
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens - First Group
ORNL-TM-1993: 1967-09
Experience with Hi-Temp Centrifugal Pumps and their Application to MSBRs
ORNL-TM-1976: 1967-10
A Literature Survey of the Fluorides and Oxyfluorides of Molybdenum
ORNL-TM-1960: 1967-12
Operation of Molten-Salt Convection Loops in the ORR
ORNL-TM-1946: 1967-08
(4.4 MB PDF)
Review of Molten-Salt Reactor Physics Calculations
ORNL-TM-1859: 1967-06-30
Maintenance Development Program for MSBRs
ORNL-TM-1858: 1967-06-09
Safety Program for MSBRs
ORNL-TM-1857: 1967-06-12
Physics Program for MSBRs
ORNL-TM-1856: 1967-05-22
Instrumentation and Controls Development for MSBRs
ORNL-TM-1854: 1967-06
Materials Development for MSBRs
ORNL-TM-1853: 1967-06-06
Chemical Research and Development for MSBRs
ORNL-TM-1852: 1967-06
Fuel and Blanket Processing Development for MSBRs
ORNL-TM-1851: 1967-06-12
Summary of the Objectives, Design, and a Program of Development of MSBRs
ORNL-TM-1810: 1967-07
A Model for Computing the Migration of Very Short-Lived Noble Gases into MSRE Graphite
ORNL-TM-1796: 1967-03-10
The Reactivity Balance in the MSRE
ORNL-TM-1730: 1967-03
Considerations of Low-Pressure Distillation of MSBR Fuels
ORNL-TM-1647: 1966-10-13
Experimental Dynamic Analysis of the MSRE
ORNL-TM-1626: 1966-10
Period Measurements on the MSRE During Fuel Circulation: Theory and Experiment
ORNL-TM-1623: 1966-09-07
Tests of Various Particle Filters for Removal of Oil Mists and Hydrocarbon Vapor
ORNL-TM-1545: 1967-09
Design Study of a Heat-Exchange System for One MSBR Concept
ORNL-TM-1543: 1966-06-01
Removal of Protactinium from Molten Fluoride Breeder Blanket Mixtures
ORNL-TM-1467: 1966-03-24
Summary of Molten-Salt Breeder Reactor Design Studies
ORNL-TM-1445: 1966-04-05
Simulators for Training MSRE Operators
ORNL-TM-1437: 1966-04
A Study of Lead and Lead-Salt Corrosion in Thermal-Convection Loops
ORNL-TM-1129: 1965-05-07
Oxide Chemistry and Thermodynamics of Molten LiF-BeF2 by Equilibriation with Gaseous H2O-HF Mixtures
ORNL-TM-1070: 1965-12
Stability Analysis of the MSRE
ORNL-TM-1060: 1965-09
Molten-Salt Converter Reactor: Design Study and Power Cost Estimates for a 1000 MWe Station
ORNL-TM-1051: 1965-03-11
Reconstitution of MSR Fuel by Reducing UF6 Gas to UF4 in a Molten Salt
ORNL-TM-1023: 1965-02
Tube Plugging in the MSRE Primary Heat Exchanger
ORNL-TM-1017: 1965-02
Tensile and Creep Properties of INOR-8 for the MSRE
ORNL-TM-0935: 1964-09-11
MSRE Neutron Source Requirements
ORNL-TM-0911: 1965-01
MSRE Design and Operations Report Part XI: Test Program
ORNL-TM-0910: 1965-01
MSRE Design and Operations Report Part X: Maintenance Equipment and Procedures
ORNL-TM-0909: 1965-01
MSRE Design and Operations Report Part IX: Safety Procedures and Emergency Plans
ORNL-TM-0907(rev): 1968-12-28
MSRE Design and Operations Report Part VII: Fuel Handling and Processing Plant (revision)
ORNL-TM-0907: 1965-01
MSRE Design and Operations Report Part VII: Fuel Handling and Processing Plant
ORNL-TM-0733(rev 3): 1969-07-25
MSRE Design and Operations Report Part VI: Operating Limits (Revision 3)
ORNL-TM-0733(rev 2): 1966-09-19
MSRE Design and Operations Report Part VI: Operating Limits (Revision 2)
ORNL-TM-0733(rev): 1965-08-03
MSRE Design and Operations Report Part VI: Operating Limits (Revision)
ORNL-TM-0733: 1965-01
MSRE Design and Operations Report Part VI: Operating Limits
ORNL-TM-0732: 1965-01
MSRE Design and Operations Report Part V: Reactor Safety Analysis Report
ORNL-TM-0730: 1965-01
MSRE Design and Operations Report Part III: Nuclear Analysis
ORNL-TM-0729B: 1965-01
MSRE Design and Operations Report Part IIB: Nuclear and Process Instrumentation
ORNL-TM-0729A: 1965-01
MSRE Design and Operations Report Part IIA: Nuclear and Process Instrumentation
ORNL-TM-0728: 1965-01
MSRE Design and Operations Report Part I: Description of Reactor Design
ORNL-TM-0611: 1963-08-27
Inherent Neutron Sources in Clean MSRE Fuel Salt
ORNL-TM-0528: 1963-05-01
Design and Operation of Forced-Circulation Corrosion Testing Loops with Molten Salt
ORNL-TM-0522: 1962-10-10
Design Studies and Cost Estimates of Two Fluoride Volatility Plants
ORNL-TM-0500: 1963-03-13
Radiation Chemistry of MSR System
ORNL-TM-0497: 1966-08-16
Analysis of Filling Accidents in MSRE
ORNL-TM-0458: 1962-12-14
Some Chemical Aspects of Molten-Salt Reactor Safety
ORNL-TM-0380: 1962-10-13
Prediction of Effective Yields of Delayed Neutrons in MSRE
ORNL-TM-0379: 1962-10-15
Temperature and Reactivity Coefficient Averaging in the MSRE
ORNL-TM-0378: 1962-11-05
Temperatures in the MSRE Core During Steady-State Power Operations
ORNL-TM-0328: 1962-09-19
Corrosion Behavior of Reactor Materials in Fluoride Salt Mixtures
ORNL-TM-0251: 1962-05-15
Safety Calculations for MSRE
ORNL-TM-0202: 1969-05
Corrosion Behavior of Nickel-Molybdenum Alloys in Fused Fluoride Mixtures
ORNL-TM-0128: 1962-02-28
Development of Freeze Valve for Use in the MSRE
ORNL-TM-0079: 1962-03-27
Water Test Development of the Fuel Pump for the MSRE
ORNL-TM-0078: 1962-10-03
Thermal-Stress and Strain-Fatigue Analyses of the MSRE Fuel and Coolant Pump Tanks
ORNL-CF-61-8-86: 1961-08-18
Thorium Breeder Reactor Evaluation Part I: Fuel Yields and Cost of a MSBR
ORNL-CF-61-4-62: 1961-04-19
MSRE Preliminary Physics Report
ORNL-CF-60-12-111: 1960-12-13
Homogeneous Molten-Salt Reactors
ORNL-CF-60-11-108: 1960-11-30
MSRE Radiator Design
ORNL-CF-59-12-64: 1960-01-12
Molten-Salt Breeder Reactors
ORNL-CF-59-8-133: 1959-08-31
Molten Salt-Graphite Compatibility Test Results
ORNL-CF-59-2-61: 1959-04-01
Processing of Molten Salt Power Reactor Fuel
ORNL-CF-58-2-46: 1958-02-05
A Molten-Salt Natural Convection Reactor System
ORNL-CF-57-4-92: 1957-04-08
Maintenance of Various Reactor Types
ORNL-CF-53-9-84: 1953-08-14
A Reflector-Moderated, Circulating Fuel Aircraft Reactor
Thorium and other MSR Documents
ORNL 2001-1646C EFG: ORNL Presentation: 2001-10-23 (16.4 MB PDF)
"Molten Salt Reactors: Technology History, Status, and Promise", Sherrell R. Greene, Senior R&D Program Manager, ORNL
IAEA-TECDOC-1450: 2005-05 (1.9 MB PDF)
Thorium Fuel Cycle--Potential Benefits and Challenges
IAEA-TECDOC-1155: 2000-05 (8.6 MB PDF)
Thorium-based Fuel Options for the Generation of Electricity: Developments in the 1990s
WASH-1222: 1972-09 (4.4 MB PDF)
An Evaluation of the Molten Salt Breeder Reactor
WASH-1097: 1969-06 (1.9 MB PDF)
The Use of Thorium in Nuclear Power Reactors
TID-26156: 1972-02 (13.3 MB PDF)
Ebasco Services 1000 MWe MSBR Conceptual Design Study
SL-1954: 1962-06 (12.2 MB PDF)
Sargent and Lundy Capital Cost Evaluation of 1000 MWe MSCR Power Plants
TID-8507: 1959-02 (16.8 MB PDF)
Report of the Fluid Fuel Reactors Task Force
LA-1156: 1950-09 (845K PDF)
Lithium Separation by Electrolysis
NAS-NS-3063: 1986-02 (2.7 MB PDF)
The Radiochemistry of Uranium, Neptunium, and Plutonium--An Updating
NAS-NS-3060: 1974-12 (6.4 MB PDF)
The Radiochemistry of Neptunium
NAS-NS-3058: 1965-09 (7.1 MB PDF)
The Radiochemistry of Plutonium
NAS-NS-3050: 1962-03 (10.9 MB PDF)
The Radiochemistry of Uranium
NAS-NS-3025: 1960-10 (3.3 MB PDF)
The Radiochemistry of the Rare Gases
NAS-NS-3016: 1959-12 (2.4 MB PDF)
The Radiochemistry of Protactinium
NAS-NS-3013: 1960-05 (2.3 MB PDF)
The Radiochemistry of Beryllium
NAS-NS-3004: 1960-01 (2.8 MB PDF)
The Radiochemistry of Thorium
Selected MSR Documents
"The CNRS Research Program on the Thorium cycle and the Molten Salt Reactors", Thorium Cycle ‐ Molten Salt Reactors June 2008, by, Thierry Auger, Gérard Barreau, Jean-Pierre Chevalier, Xavier Doligez, Sylvie Delpech, Hubert Flocard, Bernard Haas, Daniel Heuer, Elsa Merle-Lucotte: 2008-06 (1.2 MB PDF)
Proceedings of ICAPP 2007 Nice, France, May 13-18, 2007 Paper 7186: 2008-06 (0.5 MB PDF)
"Optimized Transition from the Reactors of Second and Third Generations to the Thorium Molten Salt Reactor", E. Merle-Lucotte, D. Heuer, M. Allibert, V. Ghetta, C. Le Brun, L. Mathieu, R. Brissot, E. Liatard
International Conference on the Physics of Reactors - PHYSOR 2008, Interlaken : Suisse (2008): 2008-09 (0.3 MB PDF)
"Optimization and simplification of the concept of non-moderated Thorium Molten Salt Reactor", Elsa Merle-Lucottea, Daniel Heuer, Michel Allibert, Xavier Doligeza, Véronique Ghetta, Christian Le Brun