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


Nuclear Science and Engineering, (February 1957).
Molten Fluorides as Power Reactor Fuels
The Aircraft Reactor Experiment--Physics
The Aircraft Reactor Experiment--Design and Construction
The Aircraft Reactor Experiment--Operation


Nuclear Applications and Technology, (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



Reports related to homogenous core Fluid Fluoride Reactors (FFRs) of type "MOSEL"


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



NOTE: Molten Salt Reactors are sometimes called: "Liquid Fluoride Thorium Reactors (LFTRs)", however this subclass of MSRs is a small subset of all the MSR potential designs choices, nor has a MSR ever been constructed and operated with Thorium Tetrafluoride (ThF4). ORNL did operate 2 MSRs using Uranium Tetrafluoride (UF4) in 1954 (Aircraft Reactor Experiment - ARE) and in the late 1960s (Molten Salt Reactor Experiment - MSRE).



Many of these documents came from a set of 6 CD-ROMs, which were created because (text from Index on CD-ROMs):

"This CD-ROM product contains full-text electronic technical reports and documentation on Molten Salt Reactor Technology and the Space Reactor Power System Program for use by researchers and investigators. The CD-ROM was created to support the archiving activities of the National Aeronautics and Space Administration/Marshall Space Flight Center (NASA/MSFC) and Department of Energy/Oak Ridge National Laboratory (DOE/ORNL)."