ORNL Document Repository

Documents Related to Liquid-Halide (Fluoride and Chloride) Reactor Research and Development

 


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

Part III: Liquid Metal Fuel Reactors
Chapter 18: Liquid Metal Fuel Reactors
Chapter 19: Reactor Physics for Liquid Metal Reactors Design
Chapter 20: Composition and Properties of Liquid Metal Fuels
Chapter 21: Materials of Construction–Metallurgy
Chapter 22: Chemical Processing
Chapter 23: Engineering Design
Chapter 24: Liquid-Metal Fuel Reactor Design Study
Chapter 25: Additional Liquid Metal Reactors

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


Nuclear Applications and Technology, 10 2 (February 1971).


Experiences with Dynamic Testing Methods at the MSRE
Theoretical Dynamics Analysis of the MSRE


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-5143: 1976-11
Mass Transfer Coefficients between LiF-BeF2-ThF4 and Bismuth

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-4473: 1970-02
Encapsulation of Noble Fission Product Gases in Solid Media

ORNL-4451: 1971-07
Siting of Fuel Reprocessing Plants and Waste Management Facilities

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-4415: 1969-12
Disposal of Solid Waste from Fuel Reprocessing by Fluidized-Bed Fluoride Volatility

ORNL-4397: 1969-06
Analysis of Transients in the MSRE System with 233U Fuel

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-4345: 1969-01
Temperature Profiles within Cylinders Containing Internal Heat Sources

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: 1965-12 (49.0M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1965

ORNL-3812: 1965-05 (49.0M PDF)
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: 1964-05 (37.7M PDF)
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: 1963-12 (33.7M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending July 31, 1963

ORNL-3419: 1963-05 (30.7M PDF)
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: 1962-09 (3.6M PDF)
Recovery of PuF6 by Fluorination of Fused Fluoride Salts

ORNL-3293: 1962-10-12 (1.6M PDF)
Thermodynamic Properties of Molten-Salt Solutions

ORNL-3282: 1962-07 (26.2M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1962

ORNL-3215: 1961-12 (25.6M PDF)
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1961

ORNL-3124: 1961-06-01
INOR-8-Graphite-Fused Salt Compatibility Test

ORNL-3122: 1961-06 (33.9M PDF)
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-2751: 1959-09-16 (5.8M PDF)
Characteristics of Spherical, Homogeneous, Two-Region, Molten-Fluoride-Salt Reactors

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

ORNL-2719: 1959-08-17
Phase Equilibria in the System UF4-ThF4 and LiF-UF4-ThF4

ORNL-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: 1958-09-10 (37.5M PDF)
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-2530: 1959-11 (5.6M PDF)
Solubility and Stability of PuF3 in Fused-Alkali-Fluoride-Beryllium Fluoride Mixtures

ORNL-2474: 1958-05 (21.4M PDF)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending January 31, 1958

ORNL-2431: 1958-02-07 (10.0M PDF)
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending October 31, 1957

ORNL-2396: 1959-11 (5.2M PDF)
Guide to the Phase Diagrams of the Fluoride Systems

ORNL-2387: 1958-02 (53.7M PDF)
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 30, 1957

ORNL-2378:
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-1777: 1955-02-01 (2.23M PDF)
Fused Salt Heat Transfer Part 2: Forced Convection Heat Transfer in FLiNaK

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

ORNL-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-2009-181: 2009-08 (7.3M PDF)
An Account of ORNL’s Thirteen Nuclear Reactors

ORNL-TM-2006-114: 2006-08 (1.1M PDF)
Assessment of Nuclear Hydrogen Synergies with Energy Processes

ORNL-TM-13553: 1999-06 (4.8M PDF)
Disposition Options for Uranium-233

ORNL-TM-13552: 1998-04 (6.5M PDF)
Strategy for the Future Use and Disposition of Uranium-233

ORNL-TM-13524: 1997-11 (220K PDF)
Isotopic Dilution Requirements for 233U Criticality Safety in Processing and Disposal Facilities

ORNL-TM-13517: 1998-03 (777K PDF)
Definition of Weapons-Usable Uranium-233

ORNL-TM-13142: 1996-01 (3.4M PDF)
A Descriptive Model of the MSRE After Shutdown

ORNL-TM-12925: 1995-03 (2.7M PDF)
Materials Considerations for Molten-Salt Accelerator-Based Pu Conversion Systems

ORNL-TM-11955: 1992-02 (3.9M PDF)
Literature Information Applicable to the Reaction of Uranium Oxides with Chlorine to Prepare Uranium Tetrachloride

ORNL-TM-11792: 1991-11 (3.4M PDF)
Reaction of Uranium Oxides with Chlorine and Carbon or CO to Prepare Uranium Chlorides

ORNL-TM-9780-V1: 1986-09 (1.7M PDF)
Nuclear Power Options Viability Study–Volume I: Executive Summary

ORNL-TM-9780-V2: 1986-09 (8.0M PDF)
Nuclear Power Options Viability Study–Volume II: Reactor Concepts, Descriptions, and Assessments

ORNL-TM-9780-V3: 1986-09 (7.6M PDF)
Nuclear Power Options Viability Study–Volume III: Nuclear Discipline Topics

ORNL-TM-9780-V4: 1986-09 (6.3M PDF)
Nuclear Power Options Viability Study–Volume IV: Bibliography

ORNL-TM-9756: 1985-09 (5.0M PDF)
Extended Storage-in-Place of MSRE Fuel Salt and Flush Salt

ORNL-TM-8298: 1982-12 (3.6M PDF)
Thermal-Convection-Loop Study of the Corrosion of Fe-Ni-Cr Alloys by Molten NaNO3-KNO3

ORNL-TM-7207: 1980-07 (9.1M PDF)
Conceptual Design Characteristics of a Denatured Molten-Salt Reactor with Once-Through Fueling

ORNL-TM-6763: 1979-06
Molten Salt Processes Applied to Ceramic Fuels

ORNL-TM-6474: 1978-10 (11.9M PDF)
Radiological Assessment of Thorium Mining and Milling

ORNL-TM-6415: 1979-03 (8.9M PDF)
Development Status and Potential Program for Development of Proliferation-Resistant Molten-Salt Reactors

ORNL-TM-6413: 1978-08 (3.6M PDF)
Molten-Salt Reactors for Efficient Nuclear Fuel Utilization without Plutonium Separation

ORNL-TM-6002: 1977-10 (5.2M PDF)
Status of Tellurium-Hastelloy-N Studies in Molten-Fluoride Salts

ORNL-TM-5920: 1978-01 (5.5M PDF)
Status of Materials Development for Molten-Salt-Reactors

ORNL-TM-5783: 1977-05 (2.5M PDF)
Compatibility Studies of Potential Molten-Salt Breeder Reactor Materials in Molten Fluoride Salts

ORNL-TM-5782: 1977-04 (4.5M PDF)
The Corrosion of Type 316 Stainless Steel to Li2BeF4

ORNL-TM-5781: 1977-05 (6.8M PDF)
Corrosion of Several Metals in Supercritical Steam at 538 C

ORNL-TM-5759: 1977-04 (3.1M PDF)
Distribution and Behavior of Tritium in the Coolant-Salt Technology Facility

ORNL-TM-5682: 1977-01 (1.4M PDF)
Survey of Technology for Storage of Thermal Energy in Heat Transfer Salt

ORNL-TM-5540: 1976-11 (9.8M PDF)
System Design Description of Forced-Convection Molten-Salt Corrosion Loops MSR-FCL-3 and MSR-FCL-4

ORNL-TM-5503: 1976-11 (5.6M PDF)
Temperature Gradient Compatibility Tests of Some Refractory Metals and Alloys in Bi and Bi-Li Solutions

ORNL-TM-5335: 1976-10 (1.8M PDF)
Heat Transfer Measurements in a Forced Convection Loop with Two Molten-Fluoride Salts

ORNL-TM-5325: 1976-04 (3.7M PDF)
Evaluation of Alternate Secondary (and Tertiary) Coolants for the MSBR

ORNL-TM-5253: 1976-07 (778K PDF)
Conceptual Design of a Continuous Fluorinator Experimental Facility (CFEF)

ORNL-TM-5104: 1976-03 (4.2M PDF)
A Study of Tritium Removal from Fusion Reactor Blankets of Molten-Salt and Lithium-Aluminum

ORNL-TM-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-4308: 1973-03
Density and Viscosity of Several Molten Fluoride Mixtures

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-3359: 1971-09 (3.8M PDF)
ROD: A Nuclear and Fuel-cycle Analysis Code for Circulating-Fuel Reactors

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: 1972-05 (8.0M PDF)
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 8

ORNL-TM-3257: 1972-02-10 (6.0M PDF)
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 Hydraulic 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-2823: 1970-03
Frequency-Response Testing of the Molten-Salt Reactor Experiment

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-2696: 1969-09-03
Assessment of Molten Salts as LMFBR Intermediate Coolants

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 (1.1M PDF)
Fractional Crystallization Reactions in the System LiF-BeF2-ThF4

ORNL-TM-2578: 1969-08 (3.8M PDF)
Processing of the MSRE Flush and Fuel Salts

ORNL-TM-2571: 1969-07 (2.2M PDF)
Theoretical Dynamic Analysis of the MSRE with 233U Fuel

ORNL-TM-2511: 1969-05
Materials for Molten-Salt Reactors

ORNL-TM-2490: 1969-04 (6.5M PDF)
Compatibility of Hastelloy-N and Croloy-9M with NaBF4-NaF-KBF4 Fluoroborate Salt

ORNL-TM-2489: 1969-06-02 (1.7M PDF)
MSBR Control Studies

ORNL-TM-2486: 1969-03 (0.7M PDF)
Extraction of U, Th, and Rare Earths from Molten LiF-BeF2 into Liquid Li-Bi Solutions

ORNL-TM-2483: 1969-03
Pre- and Post-Irradiation Mechanical Properties of Hastelloy-N Welds

ORNL-TM-2478: 1969-03 (3.4M PDF)
Design, Construction, and Testing of a Large Molten Salt Filter

ORNL-TM-2405: 1969-01 (2.3M PDF)
Dynamic Analysis of a Salt Supercritical Water Heat Exchanger and Throttle used with MSRE

ORNL-TM-2392: 1969-01
Diffusion of Titanium in Modified Hastelloy-N

ORNL-TM-2373: 1968-12 (1.9M PDF)
Bubbles, Drops, and Entrainment in Molten Salts

ORNL-TM-2359: 1969-02 (12.9M PDF)
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens – Second Group

ORNL-TM-2335: 1969-01 (0.8M PDF)
Solubility of Cerium Trifluoride in Molten Mixtures of LiF, BeF2, and ThF4

ORNL-TM-2318: 1969-02-06 (1.7M PDF)
Determination of the Void Fraction in the MSRE Using Small Induced Pressure Perturbations

ORNL-TM-2316: 1968-08 (2.1M PDF)
Physical Properties of Molten-Salt Reactor Fuel, Coolant, and Flush Salts

ORNL-TM-2315: 1968-08-27 (1.4M PDF)
Measurement of Helium Void Fraction in the MSRE Fuel Salt using Neutron-Noise Analysis

ORNL-TM-2305: 1968-12 (2.8M PDF)
Postirradiation Tensile and Creep-Rupture Properties of Incoloy 800 at 700 and 760 C

ORNL-TM-2304: 1968-09 (1.2M PDF)
MSRE Design and Operations Report Part XI-A: Test Program for 233U Operations

ORNL-TM-2282: 1968-07-10 (0.9M PDF)
Preliminary Study of a Molten-Salt Burst Reactor

ORNL-TM-2258: 1968-09 (4.7M PDF)
Irradiation Behavior of Cladding and Structural Materials

ORNL-TM-2256: 1968-06-20 (2.0M PDF)
Chemical Feasibility of Fueling Molten-Salt Reactors with PuF3

ORNL-TM-2245: 1968-07-23 (1.9M PDF)
Removal of 135Xe from Circulating Fuel Salt of the MSBR by Mass Transfer to Helium Bubbles

ORNL-TM-2238: 1968-07 (0.6M PDF)
Proton Reaction Analysis for Lithium and Fluorine in Graphite using a Slit-Scanning Technique

ORNL-TM-2213: 1968-11 (7.7M PDF)
Design of an Engineering-Scale, Vacuum Distillation Experiment for MSR Fuel

ORNL-TM-2180: 1968-03-26 (1.0M PDF)
Electrical Conductivity of Molten Fluorides: A Review

ORNL-TM-2136: 1969-02 (6.5M PDF)
Graphite Behavior and its Effects on MSBR Performance

ORNL-TM-2111: 1968-02 (4.6M PDF)
MSRE Design and Operations Part Report V-A: Safety Analysis of Operation with 233U

ORNL-TM-2098: 1968-01-03 (3.2M PDF)
Tube Vibration in MSRE Primary Heat Exchanger

ORNL-TM-2058: 1968-01 (2.0M PDF)
Measurement of Relative Volatilities of Rare-Earth Fluorides in Mixtures of LiF and BeF2

ORNL-TM-2036: 1967-11-02 (0.7M PDF)
Reduction of Iron Dissolved in Molten LiF-ThF4

ORNL-TM-2032: 1967-11-01 (2.3M PDF)
Closed-Circuit Television Viewing in Maintenance of Radioactive Systems at ORNL

ORNL-TM-2029: 1967-11 (4.0M PDF)
Investigation of One Concept of a Thermal Shield for the Room Housing an MSBR

ORNL-TM-2021: 1969-05
Corrosion Behavior of Nickel-Molybdenum Alloys in Fused Fluoride Mixtures

ORNL-TM-1997: 1967-11 (7.4M PDF)
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens – First Group

ORNL-TM-1993: 1967-09 (2.4M PDF)
Experience with Hi-Temp Centrifugal Pumps and their Application to MSBRs

ORNL-TM-1976: 1967-10 (1.2M PDF)
A Literature Survey of the Fluorides and Oxyfluorides of Molybdenum

ORNL-TM-1960: 1967-12 (4.6M PDF)
Operation of Molten-Salt Convection Loops in the ORR

ORNL-TM-1946: 1967-08 (4.4M PDF)
Review of Molten-Salt Reactor Physics Calculations

ORNL-TM-1859: 1967-06-30 (1.7M PDF)
Maintenance Development Program for MSBRs

ORNL-TM-1858: 1967-06-09 (3.6M PDF)
Safety Program for MSBRs

ORNL-TM-1857: 1967-06-12 (3.6M PDF)
Physics Program for MSBRs

ORNL-TM-1856: 1967-05-22 (3.2M PDF)
Instrumentation and Controls Development for MSBRs

ORNL-TM-1855: 1967-06-30 (6.8M PDF)
Components and Systems Development for MSBRs

ORNL-TM-1854: 1967-06 (10.7M PDF)
Materials Development for MSBRs

ORNL-TM-1853: 1967-06-06 (8.4M PDF)
Chemical Research and Development for MSBRs

ORNL-TM-1852: 1967-06 (4.2M PDF)
Fuel and Blanket Processing Development for MSBRs

ORNL-TM-1851: 1967-06-12 (6.6M PDF)
Summary of the Objectives, Design, and a Program of Development of MSBRs

ORNL-TM-1810: 1967-07 (1.2M PDF)
A Model for Computing the Migration of Very Short-Lived Noble Gases into MSRE Graphite

ORNL-TM-1796: 1967-03-10 (4.9M PDF)
The Reactivity Balance in the MSRE

ORNL-TM-1730: 1967-03 (3.0M PDF)
Considerations of Low-Pressure Distillation of MSBR Fuels

ORNL-TM-1647: 1966-10-13 (2.4M PDF)
Experimental Dynamic Analysis of the MSRE

ORNL-TM-1626: 1966-10 (2.7M PDF)
Period Measurements on the MSRE During Fuel Circulation: Theory and Experiment

ORNL-TM-1623: 1966-09-07 (3.4M PDF)
Tests of Various Particle Filters for Removal of Oil Mists and Hydrocarbon Vapor

ORNL-TM-1545: 1967-09 (8.7M PDF)
Design Study of a Heat-Exchange System for One MSBR Concept

ORNL-TM-1543: 1966-06-01 (1.4M PDF)
Removal of Protactinium from Molten Fluoride Breeder Blanket Mixtures

ORNL-TM-1467: 1966-03-24 (3.7M PDF)
Summary of Molten-Salt Breeder Reactor Design Studies

ORNL-TM-1445: 1966-04-05 (1.1M PDF)
Simulators for Training MSRE Operators

ORNL-TM-1437: 1966-04 (2.9M PDF)
A Study of Lead and Lead-Salt Corrosion in Thermal-Convection Loops

ORNL-TM-1341: 1966-01
Studies of the Carbon Distribution in Hastelloy-N

ORNL-TM-1129: 1965-05-07 (8.1M PDF)
Oxide Chemistry and Thermodynamics of Molten LiF-BeF2 by Equilibriation with Gaseous H2O-HF Mixtures

ORNL-TM-1070: 1965-12 (4.9M PDF)
Stability Analysis of the MSRE

ORNL-TM-1060: 1965-09 (18.8M PDF)
Molten-Salt Converter Reactor: Design Study and Power Cost Estimates for a 1000 MWe Station

ORNL-TM-1051: 1965-03-11 (0.7M PDF)
Reconstitution of MSR Fuel by Reducing UF6 Gas to UF4 in a Molten Salt

ORNL-TM-1023: 1965-02 (1.6M PDF)
Tube Plugging in the MSRE Primary Heat Exchanger

ORNL-TM-1017: 1965-02 (1.3M PDF)
Tensile and Creep Properties of INOR-8 for the MSRE

ORNL-TM-0935: 1964-09-11 (2.4M PDF)
MSRE Neutron Source Requirements

ORNL-TM-0911: 1965-01 (5.4M PDF)
MSRE Design and Operations Report Part XI: Test Program

ORNL-TM-0910: 1965-01 (12.3M PDF)
MSRE Design and Operations Report Part X: Maintenance Equipment and Procedures

ORNL-TM-0909: 1965-01 (3.4M PDF)
MSRE Design and Operations Report Part IX: Safety Procedures and Emergency Plans

ORNL-TM-0907(rev): 1968-12-28 (5.9M PDF)
MSRE Design and Operations Report Part VII: Fuel Handling and Processing Plant (revision)

ORNL-TM-0907: 1965-01 (7.9M PDF)
MSRE Design and Operations Report Part VII: Fuel Handling and Processing Plant

ORNL-TM-0733(rev 3): 1969-07-25 (0.6M PDF)
MSRE Design and Operations Report Part VI: Operating Limits (Revision 3)

ORNL-TM-0733(rev 2): 1966-09-19 (0.4M PDF)
MSRE Design and Operations Report Part VI: Operating Limits (Revision 2)

ORNL-TM-0733(rev): 1965-08-03 (0.3M PDF)
MSRE Design and Operations Report Part VI: Operating Limits (Revision)

ORNL-TM-0733: 1965-01 (0.3M PDF)
MSRE Design and Operations Report Part VI: Operating Limits

ORNL-TM-0732: 1965-01 (20.7M PDF)
MSRE Design and Operations Report Part V: Reactor Safety Analysis Report

ORNL-TM-0730: 1965-01 (13.9M PDF)
MSRE Design and Operations Report Part III: Nuclear Analysis

ORNL-TM-0729B: 1965-01 (64.9M PDF)
MSRE Design and Operations Report Part IIB: Nuclear and Process Instrumentation

ORNL-TM-0729A: 1965-01 (42.6M PDF)
MSRE Design and Operations Report Part IIA: Nuclear and Process Instrumentation

ORNL-TM-0728: 1965-01 (40.4M PDF)
MSRE Design and Operations Report Part I: Description of Reactor Design

ORNL-TM-0611: 1963-08-27 (0.6M PDF)
Inherent Neutron Sources in Clean MSRE Fuel Salt

ORNL-TM-0607: 1963-08-06
Mechanical Properties of INOR-8 Cast Metal

ORNL-TM-0528: 1963-05-01 (2.1M PDF)
Design and Operation of Forced-Circulation Corrosion Testing Loops with Molten Salt

ORNL-TM-0522: 1962-10-10 (5.0M PDF)
Design Studies and Cost Estimates of Two Fluoride Volatility Plants

ORNL-TM-0500: 1963-03-13 (4.0M PDF)
Radiation Chemistry of MSR System

ORNL-TM-0497: 1966-08-16 (2.5M PDF)
Analysis of Filling Accidents in MSRE

ORNL-TM-0458: 1962-12-14 (0.7M PDF)
Some Chemical Aspects of Molten-Salt Reactor Safety

ORNL-TM-0380: 1962-10-13 (1.5M PDF)
Prediction of Effective Yields of Delayed Neutrons in MSRE

ORNL-TM-0379: 1962-10-15 (2.3M PDF)
Temperature and Reactivity Coefficient Averaging in the MSRE

ORNL-TM-0378: 1962-11-05 (3.3M PDF)
Temperatures in the MSRE Core During Steady-State Power Operations

ORNL-TM-0328: 1962-09-19 (1.6M PDF)
Corrosion Behavior of Reactor Materials in Fluoride Salt Mixtures

ORNL-TM-0269: 1962-07-05 (5.0M PDF)
576 MWt Natural Convection Molten-Salt Reactor Study

ORNL-TM-0251: 1962-05-15 (10.9M PDF)
Safety Calculations for MSRE

ORNL-TM-0203: 1962-04-06 (12.8M PDF)
MURGATROYD–An IBM 7090 Program for the Analysis of the Kinetics of the MSRE

ORNL-TM-0202: 1969-05 (4.5M PDF)
Corrosion Behavior of Nickel-Molybdenum Alloys in Fused Fluoride Mixtures

ORNL-TM-0128: 1962-02-28 (3.9M PDF)
Development of Freeze Valve for Use in the MSRE

ORNL-TM-0079: 1962-03-27 (2.7M PDF)
Water Test Development of the Fuel Pump for the MSRE

ORNL-TM-0078: 1962-10-03 (2.7M PDF)
Thermal-Stress and Strain-Fatigue Analyses of the MSRE Fuel and Coolant Pump Tanks

ORNL-NUREG-TM-12: 1977-02 (5.7M PDF)
Carbon-14 Production in Nuclear Reactors

ORNL-MIT-117: 1970-11-18 (5.7M PDF)
Removal of Tritium from MSBR Fuel


ORNL Central Files Related to the Molten-Salt Reactor Program


ORNL-CF-70-10-14: 1970-10-09
Plans for the MSRE during the Period Between Examination and Ultimate Disposal

ORNL-CF-70-9-3: 1970-09-01
Critique of the MSRE: A Collection of Comments Submitted by Persons Associated with the Reactor

ORNL-CF-68-5-11: 1968-05-01
Performance of MSRE Nuclear Power Control Systems

ORNL-CF-67-8-10: 1967-08-01
The Program Planned for the Molten-Salt Reactor Experiment

ORNL-CF-66-2-67: 1966-02-11
Analysis of MSRE Zero-Power Flux Noise Using Digital Techniques

ORNL-CF-65-10-18: 1965-10-29
Results of Neutron Fluctuation Measurements Made During the MSRE Zero-Power Experiment

ORNL-CF-65-8-32: 1965-08-16
Preliminary Report on Results of MSRE Zero-Power Experiments

ORNL-CF-65-3-1: 1965-03-03
Comparison of Calculations and Uncertainties in the Temperature Coefficients of Reactivity in the MSRE

ORNL-CF-63-9-20: 1963-09-04
A Literature Survey of Thermal and Physical Properties of Molten Fluoride and Chloride Salt Mixtures

ORNL-CF-63-2-18: 1963-02-14
Modifications to Specifications for MSRE Graphite

ORNL-CF-62-11-69: 1962-11-12
Preliminary Equations to Describe Iodine and Xenon Behavior in the MSRE

ORNL-CF-61-12-50: 1961-12-26
MSRE Analog Computer Simulation of the System with a Servo Controller

ORNL-CF-61-10-39: 1961-10-11
Delayed Neutron Losses in Circulating Fuel Reactors

ORNL-CF-61-8-86: 1961-08-18 (10.2 PDF)
Thorium Breeder Reactor Evaluation Part I: Fuel Yields and Cost of a MSBR

ORNL-CF-61-4-62: 1961-04-19 (0.5M PDF)
MSRE Preliminary Physics Report

ORNL-CF-60-12-111: 1960-12-13 (0.4M PDF)
Homogeneous Molten-Salt Reactors

ORNL-CF-60-11-108: 1960-11-30 (1.0M PDF)
MSRE Radiator Design

ORNL-CF-60-11-20: 1960-11-04
MSRE Analog Computer Simulation of a Loss-of-Flow Accident in the Secondary System

ORNL-CF-60-6-97: 1960-06-28
Molten Salt Reactors: Report for 1960 Ten-Year-Plan Evaluation

ORNL-CF-60-3-31: 1960-03-15
Interim Report on Fluid-Fuel Thermal Breeder Reactors

ORNL-CF-59-12-64: 1960-01-12 (1.7M PDF)
Molten-Salt Breeder Reactors

ORNL-CF-59-8-133: 1959-08-31 (1.0M PDF)
Molten Salt-Graphite Compatibility Test Results

ORNL-CF-59-2-61: 1959-04-01 (1.4M PDF)
Processing of Molten Salt Power Reactor Fuel

ORNL-CF-59-1-26: 1959-01-13 (1.4M PDF)
Preliminary Study of a Graphite-Moderated Molten-Salt Power Reactor

ORNL-CF-59-1-13: 1959-02-24 (0.3M PDF)
Fuel Cycle Costs in a Graphite-Moderated Slightly-Enriched Fused-Salt Reactor

ORNL-CF-58-12-79: 1958-12-15 (0.9M PDF)
The Need for U-233 Breeding

ORNL-CF-58-10-60: 1958-10-17 (3.3M PDF)
Survey of Low-Enrichment Molten-Salt Reactors

ORNL-CF-58-10-37: 1958-10-08 (0.9M PDF)
U233 Breeders–Commentary and General Remarks

ORNL-CF-58-2-46: 1958-02-05 (2.5M PDF)
A Molten-Salt Natural Convection Reactor System

ORNL-CF-57-12-29: 1957-12-02 (0.4M PDF)
Declassification of Molten Salt Reactors

ORNL-CF-57-10-41: 1957-10-10 (0.8M PDF)
Molten Salts for Civilian Power

ORNL-CF-57-8-7: 1957-08 (13.3M PDF)
ORSORT Study: High Performance Marine Reactor

ORNL-CF-57-4-92: 1957-04-08 (2.0M PDF)
Maintenance of Various Reactor Types

ORNL-CF-57-4-27: 1957-04-29
A Preliminary Study of Molten-Salt Power Reactors

ORNL-CF-57-3-31: 1957-03-08
Fused Salt Power Reactor Study: Discussion Meeting 8

ORNL-CF-57-2-65: 1957-02-14
Fused Salt Power Reactor Study: Discussion Meeting 7

ORNL-CF-57-1-135: 1957-01-30
Fused Salt Power Reactor Study: Discussion Meeting 6

ORNL-CF-57-1-57: 1957-01-17
Power Reactor Based on Fused Salt Technology

ORNL-CF-56-12-101: 1956-12-29
Fused Salt Power Reactor Study: Discussion Meeting 5

ORNL-CF-56-12-35: 1956-12-11
Fused Salt Power Reactor Study: Discussion Meeting 4

ORNL-CF-56-11-110: 1956-10-29
Fused Salt Power Reactor Study: Discussion Meeting 3

ORNL-CF-56-9-107: 1956-09-26
Proposal for Fused Salt Power Reactor Study Group

ORNL-CF-56-9-32: 1956-09-11
Fused Salt Power Reactor Study: Discussion Meeting 2

ORNL-CF-56-8-208: 1956-08
ORSORT Study: 600 MW Fused Salt Homogeneous Reactor Power Plant

ORNL-CF-56-8-204: 1956-08 (10.9M PDF)
ORSORT Study: Fused Salt Fast Breeder

ORNL-CF-56-7-114: 1956-07-18
Fused Salt Power Reactor Study: Discussion Meeting 1

ORNL-CF-56-5-65: 1956-05-14
Fused Salt Heat Transfer

ORNL-CF-56-4-173: 1956-04-26
Molten Salt Requirements for Pratt and Whitney Aircraft

ORNL-CF-56-3-117: 1956-03-23
Feasibility of Molten Salt Power Reactors

ORNL-CF-56-2-80: 1956-02-17
Fused Salt Processing: Problem Statement

ORNL-CF-53: 1953-08-20
ORSORT Study: Circulating Fluoride Reactor for a Submarine

ORNL-CF-53-9-84: 1953-08-14 (12.0M PDF)
ORSORT Study: Reflector-Moderated, Circulating Fuel Aircraft Reactor


Liquid-Chloride Reactors


Dr. Eric Ottewitte, INEL: 1992-04 (5.2M PDF)
Cursory First Look at the Molten Chloride Fast Reactor as an Alternative to the Conventional BATR Concept

Dr. Eric Ottewitte, UCLA: 1982 (11.1M PDF)
Configuration of a Molten Chloride Fast Reactor on a Thorium Fuel Cycle to Current Nuclear Fuel Cycle Concerns

EIR-411: 1980-07 (2.2M PDF)
Reactor with Very Low Fission Product Inventory

EIR-332: 1978-01 (7.0M PDF)
Fast Reactors Using Molten Chloride Salts as Fuel: Final Report (1972-1977)

EIR-276: 1976-04
Breeding in Molten-Salt Reactors

EIR-270: 1975-02 (1.5M PDF)
Transmutation of Fission Products in a Liquid-Fuelled Fast Fission Reactor with Thermal Column

EIR-267: 1974-12 (1.1M PDF)
Chemical State of Sulphur Obtained by the 35Cl(n,p)35S Reaction During In-Pile Irradiation

EIR-259: 1975-09 (1.3M PDF)
A High-Flux Fast Molten Salt Reactor for the Transmutation of 137Ce and 90Sr

AEEW-R956: 1974-08 (4.4M PDF)
An Assessment of a 2500 MWe Molten Chloride Salt Fast Reactor

EIR-257: 1974-05 (1.4M PDF)
The Possibility of Continuous In-core Gaseous Extraction of Volatile Fission Products in a Molten Fuel Reactor

EIR-249: 1974-01 (2.5M PDF)
A Molten Salt Fast Thermal Reactor System with no Waste

ANSE-1-277: 1974 (156K PDF)
Molten Plutonium Chloride Fast Breeder Reactor Cooled by Molten Uranium Chloride

NED-5-109: 1967 (396K PDF)
New Boiling Salt Fast Breeder Reactor Concepts

NA-3-540: 1967 (168K PDF)
Fuel Properties and Nuclear Performance of Fast Reactors Fueled with Molten Chlorides

NSE-23-189: 1965 (102K PDF)
Fission Product Effects in Molten Chloride Fast-Reactor Fuels

ANL-6792: 1963-10 (116K PDF)
Molten-Salt Fast Reactors

MSR-63-53: 1963-10-31 (62K PDF)
Thermodynamic Stability of Metals and Their Chlorides in the Presence of UCl3 and PuCl3

MIT-5001: 1952-10-15 (6.3M PDF)
Chemical Problems of Non-Aqueous Fluid-Fuel Reactors

MIT-5000: 1952-10-15 (12.0M PDF)
Nuclear Problems of Non-Aqueous Fluid-Fuel Reactors


Fluoride-Salt-Cooled, Solid-Fueled Reactors


ORNL-TM-2010-199: 2010-12 (8.5M PDF)
Pre-Conceptual Design of a Fluoride-Salt-Cooled Small Modular Reactor (SmAHTR)

ORNL-TM-2006-92: 2006-06 (5.8M PDF)
Refueling Options and Considerations for Liquid-Salt-Cooled VHTRs

ORNL-TM-2006-69: 2006-06 (1.2M PDF)
Assessment of Candidate Molten-Salt Coolants for the NGNP/NHI Heat-Transfer Loop

ORNL-TM-2006-12: 2006-03 (1.2M PDF)
Assessment of Candidate Molten-Salt Coolants for the AHTR

 


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
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-1184: 1972-01 (2.3M PDF)
Updated (1970) Cost-Benefit Analysis of the US Breeder Reactor Program

WASH-1126: 1969-04 (10.7M PDF)
Cost-Benefit Analysis of the US Breeder Reactor Program

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

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

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

TID-8507: 1959-02 (16.8M 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