Documents Related to Fluid Fluorides and Fluid Chloride Reactor Research and Development, AKA, Molten Salt Reactors (MSRs)

Nuclear Science and Engineering, 2 2 (February 1957).
Molten Fluorides as Power Reactor Fuels
The Aircraft Reactor Experiment--Design and Construction
The Aircraft Reactor Experiment--Physics
The Aircraft Reactor Experiment--Operation
Fluid Fuel Reactors, Addison-Wesley, 1958.
Part I: Aqueous Homogeneous Reactors
Chapter 1: Homogeneous Reactors and their Development
Chapter 2: Nuclear Characteristics of One- and Two-Region Homogeneous Reactors
Chapter 3: Properties of Aqueous Fuel Solutions
Chapter 4: Technology of Aqueous Suspensions
Chapter 5: Integrity of Metals in Homogeneous Reactor Media
Chapter 6: Chemical Processing
Chapter 7: Design and Construction of Experimental Homogeneous Reactors
Chapter 8: Component Development
Chapter 9: Large-Scale Homogeneous Reactor Studies
Chapter 10: Homogeneous Reactor Cost Studies
Part I Index

Part II: Molten-Salt Reactors
Chapter 11: Introduction
Chapter 12: Chemical Aspects of Molten Fluoride Salt Reactor Fuels
Chapter 13: Construction Materials for Molten-Salt Reactors
Chapter 14: Nuclear Aspects of Molten-Salt Reactors
Chapter 15: Equipment for Molten-Salt Reactors Heat-Transfer Systems
Chapter 16: Aircraft Reactor Experiment
Chapter 17: Conceptual Design of a Power Reactor
Part II Index

Part III: Liquid Metal Fuel Reactors
Chapter 18: Liquid Metal Fuel Reactors
Chapter 19: Reactor Physics for Liquid Metal Reactors Design
Chapter 20: Composition and Properties of Liquid Metal Fuels
Chapter 21: Materials of Construction--Metallurgy
Chapter 22: Chemical Processing
Chapter 23: Engineering Design
Chapter 24: Liquid-Metal Fuel Reactor Design Study
Chapter 25: Additional Liquid Metal Reactors
Part III Index
Nuclear Applications and Technology, 8 2 (February 1970).
Preface: Molten Salt Reactors
Molten-Salt Reactors--History, Status, and Potential
Experience with the Molten-Salt Reactor Experiment
Molten-Salt Reactor Chemistry
New Developments in Materials for Molten-Salt Reactors
Engineering Development of the MSBR Fuel Recycle
Graphite and Xenon Behavior and Their Influence on Molten-Salt Reactor Design
The Design And Performance Features Of A Single-Fluid Molten-Salt Breeder Reactor
Reactor Physics and Fuel Cycle Analyses
ORNL Reports Related to Liquid-Fluoride Reactors and Technology
ORNL-6952: 1999-09 (848K PDF)
Uses For Uranium-233: What Should Be Kept for Future Needs?

ORNL-5388: 1978-12 (18.8M PDF)
Interim Assessment of the Denatured 233U Fuel Cycle

ORNL-5176: 1977-02 (4.2M PDF)
Engineering Tests of the Metal Transfer Process from MSBR Fuel Salt

ORNL-5132: 1976-08 (37.9M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 29, 1976

ORNL-5078: 1976-02 (30.4M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1975

ORNL-5047: 1975-09 (32.1M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1975

ORNL-5018: 1974-12 (49.6M PDF)
Program Plan for the Development of Molten-Salt Breeder Reactors

ORNL-5011: 1975-06 (17.9M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1974

ORNL-4995: 1975-07 (18.1M PDF)
An Assessment of Industrial Energy Options Based on Coal and Nuclear Systems

ORNL-4874: 1972-12 (13.9M PDF)
Development and Construction of a Molybdenum Test Stand

ORNL-4865: 1975-10 (12.8M PDF)
Fission Product Behavior in the MSRE

ORNL-4832: 1973-03 (36.8M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1972

ORNL-4831: 1973-02 (6.5M PDF)
Development of the Variable-Gap Technique for Measuring the Thermal Conductivity of Fluoride Salt Mixtures

ORNL-4830: 1973-01 (9.8M PDF)
The ORNL Automated Orbital Pipe Welding Systems

ORNL-4829: 1972-11 (52.8M PDF)
Intergranular Cracking of INOR-8 in the MSRE

ORNL-4812: 1972-08 (34.2M PDF)
Development Status of Molten-Salt Breeder Reactors

ORNL-4782: 1972-10 (48.1M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 29, 1972

ORNL-4762: 1972
Considerations in the Long Term Management of High-Level Active Wastes

ORNL-4728: 1972-02 (38.2M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1971

ORNL-4676: 1971-08 (57.0M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1971

ORNL-4658: 1971-12 (23.4M PDF)
Chemical Aspects of MSRE Operations

ORNL-4622: 1971-01 (34.3M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1970

ORNL-4616: 1971-01 (4.6M PDF)
Preparation and Handling of Salt Mixtures for the MSRE

ORNL-4577: 1971-08 (3.7M PDF)
Low-Pressure Distillation of a Portion of the Fuel Carrier Salt from the MSRE

ORNL-4575: 1971-06 (4.3M PDF)
Corrosion in Polythermal Loop Systems: Part II

ORNL-4574: 1971-04 (3.6M PDF)
Molten-Salt Fluoride Volatility Pilot Plant

ORNL-4548: 1970-08 (57.0M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1970

ORNL-4541: 1971-06 (13.2M PDF)
Conceptual Design Study of a Single-Fluid Molten-Salt Breeder Reactor

ORNL-4528: 1970-08 (6.9M PDF)
Two-Fluid Molten-Salt Breeder Reactor Design Study

ORNL-4449: 1970-02 (33.4M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1969

ORNL-4434: 1971-01 (3.4M PDF)
Low-Pressure Distillation of Molten Fluoride Mixtures

ORNL-4415: 1972-11 (1.2M PDF)
Liquid-Vapor Equilibria in LiF-BeF2 and LiF-BeF2-ThF4 Systems

ORNL-4396: 1969-08 (40.6M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1969

ORNL-4389: 1969-05 (5.5M PDF)
Gas Transport in MSRE Moderator Graphite: Parts II and III

ORNL-4371: 1969-03 (4.9M PDF)
Preparation of Enriching Salt 7LiF-233UF4 for Refueling the Molten Salt Reactor

ORNL-4344: 1969-02 (47.0M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1968

ORNL-4257: 1968-07 (2.1M PDF)
An EMF Study of LiF-BeF2 Solutions

ORNL-4254: 1968-08 (30.2M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 29, 1968

ORNL-4233: 1968-02 (4.8M PDF)
Zero-Power Physics Experiments on the MSRE

ORNL-4224: 1968-11 (4.3M PDF)
Fluorination of Falling Droplets of Molten Fluoride Salt as a Means of Recovering Uranium and Plutonium

ORNL-4191: 1967-12 (42.1M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1967

ORNL-4148: 1967-09 (3.4M PDF)
Gas Transport in MSRE Moderator Graphite: Part I

ORNL-4123: 1967-07 (3.7M PDF)
MSRE Control Elements: Manufacture, Inspection, Drawings and Specifications

ORNL-4119: 1967-07 (21.3M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1967

ORNL-4076: 1967-03 (17.6M PDF)
Reactor Chemistry Division: Annual Progress Report for Period Ending December 31, 1966

ORNL-4069: 1967-06 (4.0M PDF)
Development of a Model for Computing 135Xe Migration in the MSRE

ORNL-4037: 1967-01 (34.1M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1966

ORNL-3996: 1966-08 (10.5M PDF)
Design Studies of 1000 MWe Molten-Salt Breeder Reactors

ORNL-3936: 1966-06 (33.2M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1966

ORNL-3913: 1966-03 (17.1M 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 (9.4M PDF)
Preliminary Design Study of a Continuous Fluorination-Vacuum Distillation System for an MSBR

ORNL-3708: 1964-11 (66.3M 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-3419:
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending January 31, 1963

ORNL-3391: 1963-08 (3.8M PDF)
Mixtures of Metals with Molten Salts

ORNL-3373: 1962-12 (6.3M PDF)
Thermal Analysis of Fused Salt Phase Equilibria

ORNL-3369: 1962-12 (24.7M 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 (26.2M 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 (8.3M PDF)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending July 31, 1960

ORNL-2985: 1960-09 (4.7M PDF)
The Feasibility of an Unattended Nuclear Power Plant

ORNL-2982:
Self-Diffusion of Chromium in Nickel-Base Alloys

ORNL-2973: 1960-09 (13.1M PDF)
Molten-Salt Reactor Program: Quarterly Progress Report for Periods Ending January 31 and April 30, 1960

ORNL-2896: 1960-12 (7.6M PDF)
Phase Equilibria in Molten-Salt Breeder Reactor Fuels

ORNL-2890: 1960-03 (10.3M PDF)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending October 31, 1959

ORNL-2832: 1961-06 (21.4M PDF)
Corrosion Associated with Fluoridation in the ORNL Fluoride Volatility Process

ORNL-2799: 1959-10 (15.5M PDF)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending July 31, 1959

ORNL-2796: 1960-03 (3.0M PDF)
Experimental Molten-Salt-Fueled 30 MWe Power Reactor

ORNL-2723: 1959-06 (10.9M PDF)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending April 30, 1959

ORNL-2684: 1959-03 (13.0M PDF)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending January 31, 1959

ORNL-2677: 1959-09 (4.4M PDF)
Aluminum Chloride as a Thermodynamic Working Fluid and Heat Transfer Medium

ORNL-2661: 1959-04 (5.0M PDF)
The Fused-Salt/Fluoride Volatility Process for Recovering Uranium

ORNL-2658: 1959-04 (5.4M PDF)
Measurements Through a Hot Cell Window Using Optical Tooling

ORNL-2634: 1958-12 (20.6M PDF)
Molten-Salt Reactor Program Status Report

ORNL-2626: 1959-01 (12.7M PDF)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending October 31, 1958

ORNL-2605: 1959-10 (6.6M PDF)
Gas-Cooled, Molten-Salt Heat Exchanger Design Study

ORNL-2551:
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending June 30, 1958

ORNL-2548: 1959-11 (11.2M PDF)
Phase Diagrams of Nuclear Reactor Materials

ORNL-2474: 1958-05 (21.4M 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 (53.7M 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 (49.5M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1956

ORNL-2106: 1956-09 (37.6M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1956

ORNL-2095: 1956-05 (18.9M PDF)
Design Report on the Aircraft Reactor Test

ORNL-2061:
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1956

ORNL-2048: 1956-03 (5.8M PDF)
Corrosion of Materials in Fused Hydroxides

ORNL-2012:
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1955

ORNL-1947: 1955-10 (35.6M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1955

ORNL-1896: 1955-07 (48.7M 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 (19.9M PDF)
Operation of the Aircraft Reactor Experiment

ORNL-1835: 1955-01 (10.5M PDF)
Aircraft Reactor Test Hazards Summary Report

ORNL-1816: 1955-01 (43.5M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1954

ORNL-1771: 1954-10 (26.5M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1954

ORNL-1729: 1954-07 (16.8M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1954

ORNL-1721: 1954-05 (10.0M PDF)
ORNL Aircraft Nuclear Power Plant Designs

ORNL-1692: 1954-04 (17.4M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1954

ORNL-1649: 1954-01 (25.9M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1953

ORNL-1609: 1953-10 (17.0M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1953

ORNL-1556: 1953-07 (17.9M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1953

ORNL-1515: 1953-04 (38.2M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1953

ORNL-1495: 1953-03 (4.2M PDF)
General Information Concerning Hydroxides

ORNL-1491:
Corrosion by Molten Fluorides

ORNL-1490:
General Information Concerning Fluorides

ORNL-1439: 1953-01 (22.0M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1952

ORNL-1375: 1952-11 (18.6M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1952

ORNL-1294: 1952-08 (23.0M 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 (30.6M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1952

ORNL-1170: 1952-02 (35.4M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1951

ORNL-1154: 1951-12 (23.9M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1951

ANP-65:
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1951

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 (3.4M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending November 30, 1949


ORNL Technical Memoranda Related to the Molten-Salt Reactor Program
ORNL-TM-2006-12: 2006-03
Assessment of Candidate Molten-Salt Coolants for the AHTR
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 (14.5M PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 21

ORNL-TM-4870: 1976-01 (12.4M PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 20

ORNL-TM-4863: 1975-07 (5.7M PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 19

ORNL-TM-4804: 1975-04 (2.3M PDF)
A Method for Calculating the Steady-State Distribution of Tritium in an MSBR Plant

ORNL-TM-4802: 1975-06 (2.3M PDF)
The Molten-Salt Reactor Information System

ORNL-TM-4698: 1975-03 (4.7M PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 18

ORNL-TM-4286: 1972-12 (12.3M PDF)
Alloy Compatibility with LiF-BeF2 Salts Containing ThF4 and UF4

ORNL-TM-4272: 1972-12 (13.4M PDF)
Compatibility of Brazing Alloys and the Molten Salt NaBF4-NaF at 610 C

ORNL-TM-4271: 1972-12 (6.7M PDF)
Mass Transfer Between Hastelloy-N and a Molten NaBF4 Mixture in a Thermal Convection Loop

ORNL-TM-4221: 1972-12 (2.3M PDF)
A Forced-Circulation Loop for Corrosion Studies: Hastelloy-N Compatibility with NaBF4-NaF

ORNL-TM-4210: 1976-09 (2.3M PDF)
MRPP - Multi-Region Processing Plant Code

ORNL-TM-4189: 1972-12 (12.1M PDF)
Evaluation of Hastelloy-N Alloys After Nine Years Exposure to Both a Molten Fluoride Salt and Air

ORNL-TM-4188: 1972-12 (3.5M PDF)
Effect of FeF2 Addition on Mass Transfer in a Hastelloy-N/LiF-BeF2-UF4 Thermal Convection Loop System

ORNL-TM-4179: 1973-05 (1.7M PDF)
Improved Representation of Some Aspects of Circulating-Fuel Reactor Kinetics

ORNL-TM-4174: 1972-12 (33.3M PDF)
Post-Irradiation Examination of Materials from the MSRE

ORNL-TM-4172: 1972-12 (2.3M PDF)
Corrosion of Type 304L Stainless Steel and Hastelloy-N by Mixtures of BF3, Air, and Argon

ORNL-TM-4122: 1972-12 (1.5M PDF)
Development of a Venturi-Type Bubble Generator for Use in the MSR Xenon Removal System

ORNL-TM-4079: 1973-03 (4.0M PDF)
Forced-Convection Heat-Transfer Measurements with a Molten Fluoride Mixture Flowing in a Smooth Tube

ORNL-TM-4056: 1972-12 (1.5M PDF)
The Equilibrium of Dilute UF3 Solutions Contained in Graphite

ORNL-TM-4047: 1972-12 (1.7M 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 (2.7M PDF)
Zero Power Experiments with 233U in the MSRE

ORNL-TM-3939: 1972-12 (4.7M PDF)
MSR Component Replacements Using Remote Cutting and Welding Techniques

ORNL-TM-3884: 1972-12 (5.3M PDF)
The Migration of a Class of Fission Products (Noble Metals) in the MSRE

ORNL-TM-3866: 1972-10 (13.4M PDF)
Corrosion and Mass Transfer Characteristics of NaBF4-NaF in Hastelloy-N

ORNL-TM-3863: 1973-01 (6.2M PDF)
Design and Operation of a Forced-Circulation Corrosion Test Facility Employing Hastelloy-N and NaBF4 Salt

ORNL-TM-3832: 1972-06 (4.2M PDF)
Design Studies of a Molten-Salt Reactor Demonstration Plant

ORNL-TM-3777: 1972-12 (1.7M PDF)
Heat Transfer Salt for High-Temperature Steam Generation

ORNL-TM-3767: 1972-05-05 (2.5M PDF)
Hybrid Computer Simulation of the MSBR

ORNL-TM-3763: 1972-04 (0.8M PDF)
Estimated Behavior of Titanium in MSBR Chemical Processing Systems

ORNL-TM-3718: 1972-04 (6.5M PDF)
Mass Transfer Between Small Bubbles and Liquids in Cocurrent Turbulent Pipeline Flow

ORNL-TM-3609: 1971-12 (2.0M PDF)
A Study of the Adherence of Tungsten and Molybdenum Coatings

ORNL-TM-3595: 1971-12 (15.0M PDF)
Indexed Abstracts of Selected References on Molten-Salt Reactor Technology

ORNL-TM-3579: 1972-05 (4.9M PDF)
Design and Cost Study of a Fluorination-Reductive Extraction-Metal Transfer Processing Plant for the MSBR

ORNL-TM-3563: 1971-11 (1.4M PDF)
Availability of Natural Resources for Molten-Salt Breeder Reactors

ORNL-TM-3561: 1971-09 (0.9M PDF)
Remote Inspection of Welded Joints

ORNL-TM-3528: 1971-08 (1.7M PDF)
Solution of the Equation Describing the Interface Between Two Fluids for Volume and Pressure Between Drops

ORNL-TM-3524: 1971-10 (9.2M PDF)
Operation of the Sampler-Enricher in the MSRE

ORNL-TM-3488: 1971-10 (3.5M PDF)
Mass Transfer Between Hastelloy-N and Haynes Alloy No. 25 in a Molten Sodium Fluoroborate Mixture

ORNL-TM-3464: 1971-10 (5.2M PDF)
Xenon Behavior in the MSRE

ORNL-TM-3428: 1971-07 (1.3M PDF)
Estimated Cost of Adding a Third Salt-Circulation Loop for Controlling Tritium Migration in the 1000-MWe MSBR

ORNL-TM-3352: 1972-12 (11.8M PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 10

ORNL-TM-3344: 1972-09 (8.8M PDF)
Experience with Sodium Fluoroborate Circulation in an MSRE-Scale Facility

ORNL-TM-3321: 1971-07 (3.6M PDF)
Thermal Stability of Titanium-Modified Hastelloy-N at 650 and 760 C

ORNL-TM-3303: 1971-08 (1.5M PDF)
Further Discussion of Instrumentation and Controls Development Needed for the MSBR

ORNL-TM-3259:
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 (2.1M PDF)
MSRE Procedures for the Period Between Examination and Ultimate Disposal

ORNL-TM-3229: 1970-11 (2.6M PDF)
Fluid Dynamic Studies of the MSRE Core

ORNL-TM-3177: 1970-11 (2.9M PDF)
Molten-Salt Breeder Experiment Design Bases

ORNL-TM-3151: 1972-08 (8.9M PDF)
A Study of Fission Products in the Molten-Salt Reactor Experiment by Gamma Spectrometry

ORNL-TM-3145: 1971-03 (6.2M PDF)
Thermal Radiation Transfer of Afterheat in MSBR Heat Exchangers

ORNL-TM-3144: 1970-09 (2.3M PDF)
Fluorine Production and Recombination in Frozen MSR Salts after Reactor Operation

ORNL-TM-3141: 1971-12 (12.7M 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 (1.2M PDF)
MSBR Control Studies: Analog Simulation Program

ORNL-TM-3064: 1971-01 (24.1M PDF)
Influence of Ti, Zr, and Hf Additions on the Resistance of Modified Hastelloy-N to Irradiation Damage

ORNL-TM-3063: 1971-03 (11.8M PDF)
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens - Fourth Group

ORNL-TM-3053: 1970-11 (10.1M PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 1

ORNL-TM-3041: 1973-08 (5.4M PDF)
MSRE Operator Training and Operating Techniques

ORNL-TM-3039: 1973-06 (28.7M PDF)
MSRE Systems and Components Performance

ORNL-TM-3027: 1970-06 (11.5M PDF)
Spray, Mist, Bubbles, and Foam in the MSRE

ORNL-TM-3007: 1970-06 (1.8M PDF)
An Extended Hydralic Model of the MSRE Circulating Fuel System

ORNL-TM-3002: 1970-05 (2.3M PDF)
Reactor Power Measurement and Heat Transfer Performance in the MSRE

ORNL-TM-2999: 1970-04 (4.2M PDF)
Quality-Assurance Practices in Construction and Maintenance of the MSRE

ORNL-TM-2997: 1970-04 (1.2M PDF)
Experimental Dynamic Analysis of the MSRE with 233U Fuel

ORNL-TM-2987: 1970-10 (4.6M PDF)
Development of Fuel- and Coolant-Salt Centrifugal Pumps for the MSRE

ORNL-TM-2978: 1970-06 (2.3M PDF)
Compatibility of Fused Sodium Fluoroborate and BF3 Gas with Hastelloy-N Alloys

ORNL-TM-2974: 1970-04-07 (1.4M PDF)
Plans for Post-Operation Examination of the MSRE

ORNL-TM-2970: 1970-05 (1.0M PDF)
Calculated Radioactivity of MSRE Fuel Salt

ORNL-TM-2953: 1971-06 (5.3M PDF)
A New Approach to a Design of Steam Generators for Molten Salt Reactor Power Plants

ORNL-TM-2952: 1971-11 (3.1M PDF)
Parametric Survery of the Effects of Major Parameters of the Design of MSBR Heat Exchangers

ORNL-TM-2927: 1970-05 (2.1M PDF)
Control Studies of a 1000-MWe MSBR

ORNL-TM-2858: 1970-04 (4.8M PDF)
Tensile Properties of Hastelloy-N Welded After Irradiation

ORNL-TM-2815: 1971-04 (6.3M PDF)
Computer Programs for MSBR Heat Exchangers

ORNL-TM-2780: 1969-12 (6.2M PDF)
Preliminary Systems Design Description of the Salt Pump Test Stand for the MSBE

ORNL-TM-2743: 1969-12 (4.2M PDF)
Design and Construction of Core Irradiation-Specimen Array for MSRE Runs 19 and 20

ORNL-TM-2741: 1970-01 (3.3M PDF)
Catastropic Corrosion of Type 304 Stainless Steel in a System Circulating Fused Sodium Fluoroborate

ORNL-TM-2724: 1969-12 (1.2M PDF)
Compatibility of Molybdenum-Base Alloy TZM with LiF-BeF2-ThF4-UF4 at 1100 C

ORNL-TM-2712: 1969-11 (7.0M PDF)
Feasibility Study of Remote Cutting and Welding for Nuclear Plant Maintenance

ORNL-TM-2685: 1969-08 (0.8M PDF)
Inherent Neutron Source in MSRE with Clean 233U Fuel

ORNL-TM-2677: 1969-11 (3.8M PDF)
Management of Noble-Gas Fission-Product Wastes from Reprocessing Spent Fuels

ORNL-TM-2647: 1970-01 (15.1M PDF)
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens - Third Group

ORNL-TM-2643: 1969-08 (2.6M 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-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 (4.4M 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

Liquid-Chloride 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
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

Recent and Assorted Documents
FJOH-2004: 2004-08
Reactors with Molten Salts: Options and Missions
ICAPP-4152: 2004-06-13
An Advanced Molten Salt Reactor Using High-Temperature Reactor Technology
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
ANL-7092: 1965-09
Catalog of Nuclear Reactor Concepts: Part I, Section III
JPL-TR-32-198: 1962-03-15
Parametric Survey of Criticality-Limited Fast Reactors Employing Uranium Fluoride Fuels

Thorium, Hydrogen, and Assorted Documents
IAEA-TECDOC-1450: 2005-05 (1.9M PDF)
Thorium Fuel Cycle--Potential Benefits and Challenges

IAEA-TECDOC-1155: 2000-05 (8.6M PDF)
Thorium-based Fuel Options for the Generation of Electricity: Developments in the 1990s

WASH-1222: 1972-09 (4.4M PDF)
An Evaluation of the Molten Salt Breeder Reactor

WASH-1097: 1969-06 (1.9M PDF)
The Use of Thorium in Nuclear Power Reactors

TID-26156: 1972-02 (13.3M PDF)
Ebasco Services 1000 MWe MSBR Conceptual Design Study

SL-1954: 1962-06 (12.2M PDF)
Sargent and Lundy Capital Cost Evaluation of 1000 MWe MSCR Power Plants

TID-8507: 1959-02 (16.8M PDF)
Report of the Fluid Fuel Reactors Task Force

LA-1156: 1950-09 (845K PDF)
Lithium Separation by Electrolysis

NAS-NS-3063: 1986-02 (2.7M PDF)
The Radiochemistry of Uranium, Neptunium, and Plutonium--An Updating

NAS-NS-3060: 1974-12 (6.4M PDF)
The Radiochemistry of Neptunium

NAS-NS-3058: 1965-09 (7.1M PDF)
The Radiochemistry of Plutonium

NAS-NS-3050: 1962-03 (10.9M PDF)
The Radiochemistry of Uranium

NAS-NS-3025: 1960-10 (3.3M PDF)
The Radiochemistry of the Rare Gases

NAS-NS-3016: 1959-12 (2.4M PDF)
The Radiochemistry of Protactinium

NAS-NS-3013: 1960-05 (2.3M PDF)
The Radiochemistry of Beryllium

NAS-NS-3004: 1960-01 (2.8M PDF)
The Radiochemistry of Thorium

  • Practical Aspects of Liquid-Salt-Cooled Fast-Neutron Reactors
  • Molten-Salt Critical Reactors for the Transmutation of Transuranics and Fission Products
  • Potential of Thorium Molten-Salt Reactors: Detailed Calculations and Concept Evolutions in View of a Large Nuclear Energy Production
  • Perspectives on the Thorium Fuel Cycle
  • Thermochemical Hydrogen Production from Nuclear and Solar Energy
  • Densities of Molten Elements and Representative Salts
  • Table of Isotopic Masses and Natural Abundances