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msr-archive

curated documents pertaining to early molten salt reactor research.

poor text formatting in many of the publically available pdf scans of documents pertaining to early molten salt reactors make it cumbersome to sift out specific details. this repository is intending to make a searchable archive of ocr text files of documents pertaining to molten salt reactors, the need of which stem from the msre cad file project.

documents are rescanned with optical character recognition (ocr) using ocrmypdf, tesseract, and training set 'eng.traineddata'.

disclaimer: this repository is not intended to be a distribution of pdf documents, or an infringement on any possible copyright claims. for the original documents we refer to other sites, such as ornl's library catalog or energyfromthorium.

this repo uses git lfs (git large file storage) to manage version history of pdf's. so to clone this repo with the pdf's to your system you'll need to install git and git-lfs.

to search the repository for a keyword or phase it's recommended to use the atom editor's 'search in folder' function on the '/ocr' folder as is demonstrated here for the keyword 'msbr' using the plus and minus buttons at the top the context can be expanded or contracted. the individual pdf documents of interest in the '/docs' folder can then be opened with a pdf viewer. this method can be used to find documents with relevant information. be aware that the ocr is not great and there can be issues with missing spaces and wrong identification of letters and numbers, e.g. 'l00p' instead of 'loop'.

index

Nuclear Science and Engineering, 2 2 (February 1957).

article filename ocr
Molten Fluorides as Power Reactor Fuels NSE_moltenFluorides txt
The Aircraft Reactor Experiment--Design and Construction NSE_ARE_Design txt
The Aircraft Reactor Experiment--Physics NSE_ARE_Physics txt
The Aircraft Reactor Experiment--Operation SE_ARE_Operation txt

Fluid Fuel Reactors, Addison-Wesley (1958).

part filename ocr
Part I: Aqueous Homogeneous Reactors FFR_part1 txt
Part II: Molten-Salt Reactors FFR_part2 txt
Part III: Liquid Metal Fuel Reactors FFR_part3 txt

Part I: Aqueous Homogeneous Reactors

chapter filename ocr
Chapter 1: Homogeneous Reactors and their Development FFR_chap01 txt
Chapter 2: Nuclear Characteristics of One- and Two-Region Homogeneous Reactors FFR_chap02 txt
Chapter 3: Properties of Aqueous Fuel Solutions FFR_chap03 txt
Chapter 4: Technology of Aqueous Suspensions FFR_chap04 txt
Chapter 5: Integrity of Metals in Homogeneous Reactor Media FFR_chap05 txt
Chapter 6: Chemical Processing FFR_chap06 txt
Chapter 7: Design and Construction of Experimental Homogeneous Reactors FFR_chap07 txt
Chapter 8: Component Development FFR_chap08 txt
Chapter 9: Large-Scale Homogeneous Reactor Studies FFR_chap09 txt
Chapter 10: Homogeneous Reactor Cost Studies FFR_chap10 txt

Part II: Molten-Salt Reactors

chapter filename ocr
Chapter 11: Introduction FFR_chap11 txt
Chapter 12: Chemical Aspects of Molten Fluoride Salt Reactor Fuels FFR_chap12 txt
Chapter 13: Construction Materials for Molten-Salt Reactors FFR_chap13 txt
Chapter 14: Nuclear Aspects of Molten-Salt Reactors FFR_chap14 txt
Chapter 15: Equipment for Molten-Salt Reactors Heat-Transfer Systems FFR_chap15 txt
Chapter 16: Aircraft Reactor Experiment FFR_chap16 txt
Chapter 17: Conceptual Design of a Power Reactor FFR_chap17 txt

Part III: Liquid Metal Fuel Reactors

chapter filename ocr
Chapter 18: Liquid Metal Fuel Reactors FFR_chap18 txt
Chapter 19: Reactor Physics for Liquid Metal Reactors Design FFR_chap19 txt
Chapter 20: Composition and Properties of Liquid Metal Fuels FFR_chap20 txt
Chapter 21: Materials of Construction--Metallurgy FFR_chap21 txt
Chapter 22: Chemical Processing FFR_chap22 txt
Chapter 23: Engineering Design FFR_chap23 txt
Chapter 24: Liquid-Metal Fuel Reactor Design Study FFR_chap24 txt
Chapter 25: Additional Liquid Metal Reactors FFR_chap06 txt

Nuclear Applications and Technology

volume 8 2 (February 1970).

article filename ocr
Preface: Molten Salt Reactors NAT_preface txt
Molten-Salt Reactors--History, Status, and Potential NAT_MSRintro txt
Experience with the Molten-Salt Reactor Experiment NAT_MSREexperience txt
Molten-Salt Reactor Chemistry NAT_MSRchemistry txt
New Developments in Materials for Molten-Salt Reactors NAT_MSRmaterials txt
Engineering Development of the MSBR Fuel Recycle NAT_MSBRrecycle txt
Graphite and Xenon Behavior and Their Influence on Molten-Salt Reactor Design NAT_graphiteXenon txt
The Design And Performance Features Of A Single-Fluid Molten-Salt Breeder Reactor NAT_MSBRdesign txt
Reactor Physics and Fuel Cycle Analyses NAT_MSBRfuelcycle txt

volume 10 2 (February 1971).

article filename ocr
Experiences with Dynamic Testing Methods at the MSRE NAT_MSREdynamicsTesting txt
Theoretical Dynamics Analysis of the MSRE NAT_MSREdynamicsAnalysis txt

ORNL Reports Related to Liquid-Fluoride Reactors and Technology

report filename date ocr
Uses For Uranium-233: What Should Be Kept for Future Needs? ORNL-6952 1999-09 txt
Interim Assessment of the Denatured 233U Fuel Cycle ORNL-5388 1978-12 txt
Engineering Tests of the Metal Transfer Process from MSBR Fuel Salt ORNL-5176 1977-02 txt
Mass Transfer Coefficients between LiF-BeF2-ThF4 and Bismuth ORNL-5143 1976-11 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 29, 1976 ORNL-5132 1976-08 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1975 ORNL-5078 1976-02 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1975 ORNL-5047 1975-09 txt
Program Plan for the Development of Molten-Salt Breeder Reactors ORNL-5018 1974-12 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1974 ORNL-5011 1975-06 txt
An Assessment of Industrial Energy Options Based on Coal and Nuclear Systems ORNL-4995 1975-07 txt
Development and Construction of a Molybdenum Test Stand ORNL-4874 1972-12 txt
Fission Product Behavior in the MSRE ORNL-4865 1975-10 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1972 ORNL-4832 1973-03 txt
Development of the Variable-Gap Technique for Measuring the Thermal Conductivity of Fluoride Salt Mixtures ORNL-4831 1973-02 txt
The ORNL Automated Orbital Pipe Welding Systems ORNL-4830 1973-01 txt
Intergranular Cracking of INOR-8 in the MSRE ORNL-4829 1972-11 txt
Development Status of Molten-Salt Breeder Reactors ORNL-4812 1972-08 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 29, 1972 ORNL-4782 1972-10 txt
Considerations in the Long Term Management of High-Level Active Wastes ORNL-4762 1972-02 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1971 ORNL-4728 1972-02 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1971 ORNL-4676 1971-08 txt
Reactivity Balance Calculations and Long-Term Reactivity Behavior with 235U in the MSRE ORNL-4674 1972-02 txt
Chemical Aspects of MSRE Operations ORNL-4658 1971-12 txt
ORIGEN - The ORNL Isotope Generation and Depletion Code ORNL-4628 1973-05 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1970 ORNL-4622 1971-01 txt
Preparation and Handling of Salt Mixtures for the MSRE ORNL-4616 1971-01 txt
Low-Pressure Distillation of a Portion of the Fuel Carrier Salt from the MSRE ORNL-4577 1971-08 txt
Corrosion in Polythermal Loop Systems: Part II ORNL-4575 1971-06 txt
Molten-Salt Fluoride Volatility Pilot Plant ORNL-4574 1971-04 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1970 ORNL-4548 1970-08 txt
Conceptual Design Study of a Single-Fluid Molten-Salt Breeder Reactor ORNL-4541 1971-06 txt
Two-Fluid Molten-Salt Breeder Reactor Design Study ORNL-4528 1970-08 txt
Encapsulation of Noble Fission Product Gases in Solid Media ORNL-4473 1970-02 txt
Siting of Fuel Reprocessing Plants and Waste Management Facilities ORNL-4451 1970-07 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1969 ORNL-4449 1970-02 txt
Low-Pressure Distillation of Molten Fluoride Mixtures ORNL-4434 1971-01 txt
Liquid-Vapor Equilibria in LiF-BeF2 and LiF-BeF2-ThF4 Systems ORNL-4415 1972-11 txt
Disposal of Solid Waste from Fuel Reprocessing by Fluidized-Bed Fluoride Volatility ORNL-4415 1969-12 txt
Analysis of Transients in the MSRE System with 233U Fuel ORNL-4397 1969-06 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1969 ORNL-4396 1969-08 txt
Gas Transport in MSRE Moderator Graphite: Parts II and III ORNL-4389 1969-05 txt
Preparation of Enriching Salt 7LiF-233UF4 for Refueling the Molten Salt Reactor ORNL-4371 1969-03 txt
Temperature Profiles within Cylinders Containing Internal Heat Sources ORNL-4345 1969-01 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1968 ORNL-4344 1969-02 txt
Mechanical Properties of Artificial Graphites--A Survey Report ORNL-4327 1968-12 txt
An EMF Study of LiF-BeF2 Solutions ORNL-4257 1968-07 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 29, 1968 ORNL-4254 1968-08 txt
Zero-Power Physics Experiments on the MSRE ORNL-4233 1968-02 txt
Fluorination of Falling Droplets of Molten Fluoride Salt as a Means of Recovering Uranium and Plutonium ORNL-4224 1968-11 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1967 ORNL-4191 1967-12 txt
Gas Transport in MSRE Moderator Graphite: Part I ORNL-4148 1967-09 txt
MSRE Control Elements: Manufacture, Inspection, Drawings and Specifications ORNL-4123 1967-07 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1967 ORNL-4119 1967-07 txt
Reactor Chemistry Division: Annual Progress Report for Period Ending December 31, 1966 ORNL-4076 1967-03 txt
Development of a Model for Computing 135Xe Migration in the MSRE ORNL-4069 1967-06 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1966 ORNL-4037 1967-01 txt
Design Studies of 1000 MWe Molten-Salt Breeder Reactors ORNL-3996 1966-08 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1966 ORNL-3936 1966-06 txt
Reactor Chemistry Division: Annual Progress Report for Period Ending December 31, 1965 ORNL-3913 1966-03 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1965 ORNL-3872 1965-12 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1965 ORNL-3812 1965-05 txt
Rare-Earth Halides ORNL-3804 1965-05 txt
Preliminary Design Study of a Continuous Fluorination-Vacuum Distillation System for an MSBR ORNL-3791 1966-01 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending July 31, 1964 ORNL-3708 1964-11 txt
Influence of Several Metallurgical Variables on the Tensile Properties of Hastelloy N ORNL-3661 1964-08 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending January 31, 1964 ORNL-3626 1964-05 txt
Adaptation of the Fused-Salt Fluoride-Volatility Process to the Recovery of Uranium from Al-U Alloy Fuel ORNL-3596 1964-06 txt
Molten-Salt Solvents for Fluoride Volatility Processing of Al-Matrix Nuclear Fuel Elements ORNL-3594 1964-08 txt
Mechanical Properties of Some Refractory Metals and their Alloys ORNL-3593 1964-04 txt
Reduction of UF6 Retention on Beds of MgF2 Used for Removal of TcF6 ORNL-3544 1964-01 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending July 31, 1963 ORNL-3529 1963-12 txt
Fabrication of the Heat Exchanger Tube Bundle for the MSRE ORNL-3500 1963-11-22 txt
Review of Thorium Reserves in Granitic Rock and Processing of Thorium Ores ORNL-3495 1963-11-22 txt
An Experimental Study of Sorption of UF6 by NaF Pellets ORNL-3494 1963-11-14 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending January 31, 1963 ORNL-3419 1963-05 txt
Review of Electronic Absorption Spectra of Molten Salts ORNL-3411 1963-08-13 txt
Mixtures of Metals with Molten Salts ORNL-3391 1963-08 txt
Thermal Analysis of Fused Salt Phase Equilibria ORNL-3373 1962-12 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1962 ORNL-3369 1962-12 txt
Recovery of PuF6 by Fluorination of Fused Fluoride Salts ORNL-3298 1962-09 txt
Thermodynamic Properties of Molten-Salt Solutions ORNL-3293 1962-10-12 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1962 ORNL-3282 1962-07 txt
Corrosion of Mark-1 INOR-8 Hydrofluorinator and Mark III Nickel Fluorinator after 14 Dissolution Runs ORNL-3253 1962-02-09 txt
Aircraft Nuclear Propulsion Program: Semiannual Progress Report for Period Ending April 30, 1961 ORNL-3144 1961-07-11 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending August 31, 1961 ORNL-3215 1961-12 txt
INOR-8-Graphite-Fused Salt Compatibility Test ORNL-3124 1961-06-01 txt
Molten-Salt Reactor Program: Semiannual Progress Report for Period Ending February 28, 1961 ORNL-3122 1961-06 txt
Aircraft Nuclear Propulsion Program: Semiannual Progress Report for Period Ending October 31, 1960 ORNL-3029 1960-12-16 txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending July 31, 1960 ORNL-3014 1960-12 txt
The Feasibility of an Unattended Nuclear Power Plant ORNL-2985 1960-09 txt
Self-Diffusion of Chromium in Nickel-Base Alloys ORNL-2982 1961-01-20 txt
Molten-Salt Reactor Program: Quarterly Progress Report for Periods Ending January 31 and April 30, 1960 ORNL-2973 1960-09 txt
Aircraft Nuclear Propulsion Program: Semiannual Progress Report for Period Ending April 30, 1960 ORNL-2942 1960-07-12 txt
Phase Equilibria in Molten-Salt Breeder Reactor Fuels ORNL-2896 1960-12 txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending October 31, 1959 ORNL-2890 1960-03 txt
Aircraft Nuclear Propulsion Program: Semiannual Progress Report for Period Ending October 31, 1959 ORNL-2840 1959-10 txt
Corrosion Associated with Hydrofluorination in the ORNL Fluoride Volatility Process ORNL-2833 1961-11-01 txt
Corrosion Associated with Fluorination in the ORNL Fluoride Volatility Process ORNL-2832 1961-06 txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending July 31, 1959 ORNL-2799 1959-10 txt
Experimental Molten-Salt-Fueled 30 MWe Power Reactor ORNL-2796 1960-03-08 txt
Mechanical Properties of INOR-8 ORNL-2780 1961-01-10 txt
Welding of Nickel-Molybdenum Alloys ORNL-2760 1959-08-11 txt
Characteristics of Spherical, Homogeneous, Two-Region, Molten-Fluoride-Salt Reactors ORNL-2751 1959-09-16 txt
Solubility Relations Among Rare-Earth Fluorides in Selected Molten-Salt Solvents ORNL-2749 1959-10-13 txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending April 30, 1959 ORNL-2723 1959-06 txt
Phase Equilibria in the System UF4-ThF4 and LiF-UF4-ThF4 ORNL-2719 1959-08-17 txt
Aircraft Nuclear Propulsion Program: Semiannual Progress Report for Period Ending March 31, 1959 ORNL-2711 1959-03 txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending January 31, 1959 ORNL-2684 1959-03 txt
Aluminum Chloride as a Thermodynamic Working Fluid and Heat Transfer Medium ORNL-2677 1959-09 txt
The Fused-Salt/Fluoride Volatility Process for Recovering Uranium ORNL-2661 1959-04 txt
Measurements Through a Hot Cell Window Using Optical Tooling ORNL-2658 1959-04 txt
Molten-Salt Reactor Program Status Report ORNL-2634 1958-12 txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending October 31, 1958 ORNL-2626 1959-01 txt
Gas-Cooled, Molten-Salt Heat Exchanger Design Study ORNL-2605 1959-10 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 30, 1958 ORNL-2599 1958-09 txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending June 30, 1958 ORNL-2551 1958-09-10 txt
Phase Diagrams of Nuclear Reactor Materials ORNL-2548 1959-11 txt
A Zero-Power Reflector-Moderated Reactor Experiment at Elevated Temperature ORNL-2536 1958-08-01 txt
Solubility and Stability of PuF3 in Fused-Alkali-Fluoride-Beryllium Fluoride Mixtures ORNL-2530 1959-11 txt
Influence of Composition upon the 1500F Creep-Rupture Strength and Microstructure of Mo-Cr-Fe-Ni-Base Alloys ORNL-2524 1959-11 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 31, 1958 ORNL-2517 1958-08-20 txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending January 31, 1958 ORNL-2474 1958-05 txt
Termination Report for Construction of the ART Facility ORNL-2465 1958-11-21 txt
ART Removal and Disassembly ORNL-2464 1960-03-04 txt
Thermal Stress Analysis of the ART Heat Exchanger Channels and Header Pipes ORNL-2442 1958-03-14 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 31, 1957 ORNL-2440 1958-04-15 txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending October 31, 1957 ORNL-2431 1958-02-07 txt
Guide to the Phase Diagrams of the Fluoride Systems ORNL-2396 1959-11 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 30, 1957 ORNL-2387 1958-02 txt
Molten-Salt Reactor Program: Quarterly Progress Report for Period Ending September 1, 1957 ORNL-2378 1957-12-27 txt
ART Fuel Pump and Xenon Removal System Development, Test Evaluation, and Aircraft Application ORNL-2376 1957-12-10 txt
Some Aspects of the Behavior of Fission Products in Molten-Fluoride Reactor Fuels ORNL-2374 1957-08-28 txt
Effect of Radiation on Corrosion of Structural Materials by Molten Fluorides ORNL-2373 1957-08-13 txt
Shield Plug Assembly for the ART Fuel Pumps ORNL-2353 1958-04-03 txt
Aircraft Reactor Experiment - Metallurgical Aspects ORNL-2349 1957-12-20 txt
Components of the Fused-Salt and Sodium Circuits of the ARE ORNL-2348 1958-02-15 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 30, 1957 ORNL-2340 1957-09-11 txt
Interim Report on Corrosion by Zirconium-Base Fluorides ORNL-2338 1961-01-03 txt
Interim Report on Corrosion by Alkali-Metal Fluorides: Work to May 1, 1953 ORNL-2337 1959-03-20 txt
Phase Equilibrium Diagrams for Fused Salt Systems ORNL-2295 1957-06-24 txt
Viscosity Measurements on Molten Fluoride Mixtures ORNL-2278 1957-06-28 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 31, 1957 ORNL-2274 1957-07-05 txt
Inconel as a Structural Material for a High-Temperature Fused-Salt Reactor ORNL-2264 1957-06-04 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 31, 1956, part 6 ORNL-2221 1957-03-26 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 31, 1956, part 1-5 ORNL-2221 1957-03-12 txt
Investigation of Fluid Flow in the ART and Other Reflector-Moderator Reactor Cores ORNL-2199 1957-04 txt
Analytical and Experimental Studies of the Temperature Structure Within the ART Core ORNL-2198 1957-01-31 txt
Optical Properties and X-Ray Diffraction Data for Some Inorganic Fluoride and Chloride Compounds ORNL-2192 1958-10-23 txt
Dissolution of U-Zr Fuel Elements in Fused NaF-ZrF4 ORNL-2183 1957-01-24 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1956 ORNL-2157 1956-12 txt
Corrosion Products Formed in the Reaction Between Fused Sodium Hydroxide and Iron-Rich Alloys of Fe, Cr, and Ni ORNL-2156 1957-04-26 txt
A Physical Property Summary for ANP Fluoride Mixtures ORNL-2150 1956-08-23 txt
Measurement and Analysis of the Holdup of Gas Mixtures by Charcoal Traps ORNL-2116 1956-07-27 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1956 ORNL-2106 1956-09 txt
Compatibility Tests of Materials for Use in Bearings, Seals, and Valves in Fused Fluoride Salts at 1200F ORNL-2103 1956-09-21 txt
Design Report on the Aircraft Reactor Test ORNL-2095 1956-05 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1956 ORNL-2061 1956-05-23 txt
Corrosion of Materials in Fused Hydroxides ORNL-2048 1956-03 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1955 ORNL-2012 1956-02-20 txt
Steady-State Control Characteristics of Chemical-Nuclear Aircraft Power Plants ORNL-1976 1956-02-29 txt
A Fluoride Fuel In-Pile Loop Experiment ORNL-1965 1957-01-15 txt
Enthalpies and Heat Capacities of Solid and Molten Fluoride Mixtures ORNL-1956 1956-01-11 txt
Fabrication of Heat Exchangers and Radiators for High-Temperature Reactor Applications ORNL-1955 1956-06-14 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1955 ORNL-1947 1955-10 txt
Application of Temperature Solutions for Forced Convection Systems with Volume Heat Sources ORNL-1933 1955-09-29 txt
A Theoretical Study of 135Xe Poisoning Kinetics in Fluid-Fueled, Gas-Sparged Nuclear Reactors ORNL-1924 1956-02-06 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1955 ORNL-1896 1955-07 txt
Disassembly and Postoperative Examination of the Aircraft Reactor Experiment ORNL-1868 1959-04-02 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1955 ORNL-1864 1955-04-21 txt
Operation of the Aircraft Reactor Experiment ORNL-1845 1955-09 txt
Aircraft Reactor Test Hazards Summary Report ORNL-1835 1955-01 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1954 ORNL-1816 1955-01 txt
Some Economic Aspects of Thorium Breeder Reactors ORNL-1810 1955-10-12 txt
Design Calculations for a Miniature High-Temperature In-Pile Circulating Fuel Loop ORNL-1808 1955-09-19 txt
Fused Salt Heat Transfer Part 2: Forced Convection Heat Transfer in FLiNaK ORNL-1777 1955-02-01 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1954 ORNL-1771 1954-10 txt
Preliminary Critical Assemblies of the Reflector Moderator Reactor ORNL-1770 1954-11-22 txt
Free Convection in Fluids Having a Volume Heat Source ORNL-1769 1954-11-15 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1954 ORNL-1729 1954-07 txt
ORNL Aircraft Nuclear Power Plant Designs ORNL-1721 1954-05 txt
Turbulent Heat Transfer from a Molten Fluoride Salt Mixture to NaK in a Double-Tube Heat Exchanger ORNL-1716 1954-11-08 txt
Optical Properties of Some Inorganic Fluoride and Chloride Compounds ORNL-1712 1954-05-05 txt
Present Status of the Investigation of Aqueous Solutions Suitable for a Thorium Breeder Blanket ORNL-1711 1954-05-10 txt
A Summary of Density Measurements on Molten Fluoride Mixtures and a Correlation for Predicting Densities ORNL-1702 1954-07-19 txt
Forced Convection Heat Transfer Between Parallel Plates and in Annuli with Volume Heat Sources within the Fluids ORNL-1701 1954-05-11 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1954 ORNL-1692 1954-04 txt
Enthalpies and Specific Heats of Alkali and Alkaline-Earth Hydroxides at High Temperatures ORNL-1653 1954-01-07 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1953 ORNL-1649 1954-01 txt
Preliminary Critical Assembly for the Aircraft Reactor Experiment ORNL-1634 1953-10-18 txt
Critical Experiments on Direct Cycle Aircraft Reactor ORNL-1615 1953-10-22 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1953 ORNL-1609 1953-10 txt
Chemical Methods for the Separation of Lithium Isotopes ORNL-1592 1953-08-18 txt
Heavy Isotope Buildup in Core of 233U Breeder ORNL-1567 1953-10-06 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1953 ORNL-1556 1953-07 txt
Thermodynamic and Heat Transfer Analysis of the Aircraft Reactor Experiment ORNL-1535 1953-08-10 txt
The Moderator Cooling System for the Reflector-Moderated Reactor ORNL-1517 1954-01-22 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1953 ORNL-1515 1953-04 txt
General Information Concerning Hydroxides ORNL-1495 1953-03 txt
Corrosion by Molten Fluorides ORNL-1491 1953-03-17 txt
General Information Concerning Fluorides ORNL-1490 1953-02-27 txt
Methods of Fabrication of Control and Safety Element Components for the ARE and HRE ORNL-1463 1953-02-26 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1952 ORNL-1439 1953-01 txt
Aircraft Reactor Experiment Hazards Summary Report ORNL-1407 1952-11 txt
Forced Convection Heat Transfer in Pipes with Volume Heat Sources within the Fluids ORNL-1395 1952-12 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1952 ORNL-1375 1952-11 txt
Turbulent Forced Convection Heat Transfer in Circular Tubes containing Molten Sodium Hydroxide ORNL-1370 1952-10 txt
Some Effects of Transmutation Products on U233 Breeder Pile Operation ORNL-1368 1952-09-23 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1952 ORNL-1294 1952-08 txt
A Design Study of a Nuclear-Powered Airplane in which Circulating Fuel is Piped Directly ORNL-1287 1953-03-31 txt
General Information Concerning Fluorides ORNL-1252 1952-02-19 txt
Reactor Program of the Aircraft Nuclear Propulsion Project ORNL-1234 1952-06-02 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1952 ORNL-1227 1952-05 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1951 ORNL-1170 1952-02 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending September 10, 1951 ORNL-1154 1951-12 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending June 10, 1951 ANP-65 1951-06 txt
An Investigation of ThF4-Fused-Salt Solutions for Homogeneous Breeder Reactors ORNL-1030 1951-06-19 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending March 10, 1951 ANP-60 1953-03 txt
Dry Fluoride Process Status Report ORNL-0980 1951-03-27 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending December 10, 1950 ORNL-0919 1951-02-26 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending August 1, 1950 ORNL-0858 1950-12-05 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending May 31, 1950 ORNL-0768 1950-08-14 txt
The Atomic Powered Aircraft, January 1950 ORNL-0684 1950-04-26 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending February 28, 1950 ORNL-0629 1950-02 txt
Aircraft Nuclear Propulsion Program: Quarterly Progress Report for Period Ending November 30, 1949 ORNL-0528 1950-01 txt

ORNL Technical Memoranda Related to the Molten-Salt Reactor Program

report filename date ocr
Disposition Options for Uranium-233 ORNL-TM-13553 1999-06 txt
Strategy for the Future Use and Disposition of Uranium-233 ORNL-TM-13552 1998-04 txt
Isotopic Dilution Requirements for 233U Criticality Safety in Processing and Disposal Facilities ORNL-TM-13524 1997-11 txt
Definition of Weapons-Usable Uranium-233 ORNL-TM-13517 1998-03 txt
A Descriptive Model of the MSRE After Shutdown ORNL-TM-13142 1996-01 txt
Materials Considerations for Molten-Salt Accelerator-Based Pu Conversion Systems ORNL-TM-12925 1995-03 txt
Tensile and Creep Tests on a Single Heat of Alloy 800H ORNL-TM-12436 1993-09 txt
Use of the MCM for Analysis of Alloy 800H Rupture Data ORNL-TM-12430 1993-09 txt
Final Analysis of ORNL Creep-Rupture and Tensile Data on 2.25 Cr-1 Mo Steel ORNL-TM-12429 1993-10 txt
Literature Information Applicable to the Reaction of Uranium Oxides with Chlorine to Prepare Uranium Tetrachloride ORNL-TM-11955 1992-02 txt
Reaction of Uranium Oxides with Chlorine and Carbon or CO to Prepare Uranium Chlorides ORNL-TM-11792 1991-11 txt
Nuclear Power Options Viability Study--Volume I: Executive Summary ORNL-TM-9780-V1 1986-09 txt
Nuclear Power Options Viability Study--Volume II: Reactor Concepts, Descriptions, and Assessments ORNL-TM-9780-V2 1986-09 txt
Nuclear Power Options Viability Study--Volume III: Nuclear Discipline Topics ORNL-TM-9780-V3 1986-09 txt
Nuclear Power Options Viability Study--Volume IV: Bibliography ORNL-TM-9780-V4 1986-09 txt
Extended Storage-in-Place of MSRE Fuel Salt and Flush Salt ORNL-TM-9756 1985-09 txt
Mechanical Properties of Inconel 617 and 618 ORNL-TM-9337 1985-02 txt
Thermal-Convection-Loop Study of the Corrosion of Fe-Ni-Cr Alloys by Molten NaNO3-KNO3 ORNL-TM-8298 1982-12 txt
Conceptual Design Characteristics of a Denatured Molten-Salt Reactor with Once-Through Fueling ORNL-TM-7207 1980-07 txt
Molten Salt Processes Applied to Ceramic Fuels ORNL-TM-6763 1979-06 txt
Radiological Assessment of Thorium Mining and Milling ORNL-TM-6474 1978-10 txt
Development Status and Potential Program for Development of Proliferation-Resistant Molten-Salt Reactors ORNL-TM-6415 1979-03 txt
Molten-Salt Reactors for Efficient Nuclear Fuel Utilization without Plutonium Separation ORNL-TM-6413 1978-08 txt
Thermodynamics of Carbon in Nickel-Based Multicomponent Solid Solutions ORNL-TM-6282 1978-04 txt
Status of Tellurium-Hastelloy-N Studies in Molten-Fluoride Salts ORNL-TM-6002 1977-10 txt
Expansion Potential for Existing Nuclear Power Station Sites ORNL-TM-5927 1977-11 txt
Status of Materials Development for Molten-Salt-Reactors ORNL-TM-5920 1978-01 txt
Compatibility Studies of Potential Molten-Salt Breeder Reactor Materials in Molten Fluoride Salts ORNL-TM-5783 1977-05 txt
The Corrosion of Type 316 Stainless Steel to Li2BeF4 ORNL-TM-5782 1977-04 txt
Corrosion of Several Metals in Supercritical Steam at 538 C ORNL-TM-5781 1977-05 txt
Distribution and Behavior of Tritium in the Coolant-Salt Technology Facility ORNL-TM-5759 1977-04 txt
Importance of Billet Microstructure in the Hot Extrusion of 2% Ti-Hastelloy N ORNL-TM-5741 1977-05 txt
Production of Homogeneous Titanium-Hastelloy N Alloys ORNL-TM-5697 1977-02 txt
Survey of Technology for Storage of Thermal Energy in Heat Transfer Salt ORNL-TM-5682 1977-01 txt
Assessment of the Thorium Fuel Cycle in Power Reactors ORNL-TM-5565 1977-01 txt
System Design Description of Forced-Convection Molten-Salt Corrosion Loops MSR-FCL-3 and MSR-FCL-4 ORNL-TM-5540 1976-11 txt
Temperature Gradient Compatibility Tests of Some Refractory Metals and Alloys in Bi and Bi-Li Solutions ORNL-TM-5503 1976-11 txt
Heat Transfer Measurements in a Forced Convection Loop with Two Molten-Fluoride Salts ORNL-TM-5335 1976-10 txt
Evaluation of Alternate Secondary (and Tertiary) Coolants for the MSBR ORNL-TM-5325 1976-04 txt
Conceptual Design of a Continuous Fluorinator Experimental Facility (CFEF) ORNL-TM-5253 1976-07 txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 23 ORNL-TM-5252 ????-?? txt
A Study of Tritium Removal from Fusion Reactor Blankets of Molten-Salt and Lithium-Aluminum ORNL-TM-5104 1976-03 txt
On Nuclear Fuel, Mass Balances, Conversion Ratio, Doubling Time, and Uncertainty ORNL-TM-5050 1976-11 txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 21 ORNL-TM-4894 1976-03 txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 20 ORNL-TM-4870 1976-01 txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 19 ORNL-TM-4863 1975-07 txt
A Method for Calculating the Steady-State Distribution of Tritium in an MSBR Plant ORNL-TM-4804 1975-04 txt
The Molten-Salt Reactor Information System ORNL-TM-4802 1975-06 txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 18 ORNL-TM-4698 1975-03 txt
Corrosion of Several Iron and Nickel-Base Alloys in Supercritical Steam at 1000F ORNL-TM-4552 1974-08 txt
Influence of Aging on the Impact Properties of Hastelloy N ORNL-TM-4380 1973-12 txt
Density and Viscosity of Several Molten Fluoride Mixtures ORNL-TM-4308 1973-03 txt
Alloy Compatibility with LiF-BeF2 Salts Containing ThF4 and UF4 ORNL-TM-4286 1972-12 txt
Compatibility of Brazing Alloys and the Molten Salt NaBF4-NaF at 610 C ORNL-TM-4272 1972-12 txt
Mass Transfer Between Hastelloy-N and a Molten NaBF4 Mixture in a Thermal Convection Loop ORNL-TM-4271 1972-12 txt
A Forced-Circulation Loop for Corrosion Studies: Hastelloy-N Compatibility with NaBF4-NaF ORNL-TM-4221 1972-12 txt
MRPP - Multi-Region Processing Plant Code ORNL-TM-4210 1976-09 txt
Evaluation of Hastelloy-N Alloys After Nine Years Exposure to Both a Molten Fluoride Salt and Air ORNL-TM-4189 1972-12 txt
Effect of FeF2 Addition on Mass Transfer in a Hastelloy N/LiF-BeF2-UF4 Thermal Convection Loop System ORNL-TM-4188 1972-12 txt
Improved Representation of Some Aspects of Circulating-Fuel Reactor Kinetics ORNL-TM-4179 1973-05 txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 17 ORNL-TM-4178 ????-?? txt
Post-Irradiation Examination of Materials from the MSRE ORNL-TM-4174 1972-12 txt
Influence of Various Alloying Additions on the Strength of Nickel-Base Alloys ORNL-TM-4173 1972-12 txt
Corrosion of Type 304L Stainless Steel and Hastelloy-N by Mixtures of BF3, Air, and Argon ORNL-TM-4172 1972-12 txt
Development of a Venturi-Type Bubble Generator for Use in the MSR Xenon Removal System ORNL-TM-4122 1972-12 txt
Forced-Convection Heat-Transfer Measurements with a Molten Fluoride Mixture Flowing in a Smooth Tube ORNL-TM-4079 1973-03 txt
The Equilibrium of Dilute UF3 Solutions Contained in Graphite ORNL-TM-4056 1972-12 txt
Molten Salts as Blanket Fluids in Controlled Fusion Reactors ORNL-TM-4047 1972-12 txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 16 ORNL-TM-4020 ????-?? txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 15 ORNL-TM-4019 ????-?? txt
Neutron-Induced Transmutation of High-Level Radioactive Waste ORNL-TM-3964 1972-12 txt
Zero Power Experiments with 233U in the MSRE ORNL-TM-3963 1972-12 txt
MSR Component Replacements Using Remote Cutting and Welding Techniques ORNL-TM-3939 1972-12 txt
The Migration of a Class of Fission Products (Noble Metals) in the MSRE ORNL-TM-3884 1972-12 txt
Corrosion and Mass Transfer Characteristics of NaBF4-NaF in Hastelloy-N ORNL-TM-3866 1972-10 txt
Design and Operation of a Forced-Circulation Corrosion Test Facility Employing Hastelloy-N and NaBF4 Salt ORNL-TM-3863 1973-01 txt
Design Studies of a Molten-Salt Reactor Demonstration Plant ORNL-TM-3832 1972-06 txt
Heat Transfer Salt for High-Temperature Steam Generation ORNL-TM-3777 1972-12 txt
Hybrid Computer Simulation of the MSBR ORNL-TM-3767 1972-05-05 txt
Estimated Behavior of Titanium in MSBR Chemical Processing Systems ORNL-TM-3763 1972-04 txt
Mass Transfer Between Small Bubbles and Liquids in Cocurrent Turbulent Pipeline Flow ORNL-TM-3718 1972-04 txt
A Study of the Adherence of Tungsten and Molybdenum Coatings ORNL-TM-3609 1971-12 txt
Indexed Abstracts of Selected References on Molten-Salt Reactor Technology ORNL-TM-3595 1971-12 txt
Design and Cost Study of a Fluorination-Reductive Extraction-Metal Transfer Processing Plant for the MSBR ORNL-TM-3579 1972-05 txt
Availability of Natural Resources for Molten-Salt Breeder Reactors ORNL-TM-3563 1971-11 txt
Remote Inspection of Welded Joints ORNL-TM-3561 1971-09 txt
The Long-Term Hazard of Radioactive Wastes Produced by Enriched Uranium, U/Pu, and Th/U Fuel Cycles ORNL-TM-3548 1971-11 txt
Solution of the Equation Describing the Interface Between Two Fluids for Volume and Pressure Between Drops ORNL-TM-3528 1971-08 txt
Operation of the Sampler-Enricher in the MSRE ORNL-TM-3524 1971-10 txt
Status of Noble-Gas Removal and Disposal ORNL-TM-3515 1971-08 txt
Mass Transfer Between Hastelloy-N and Haynes Alloy No. 25 in a Molten Sodium Fluoroborate Mixture ORNL-TM-3488 1971-10 txt
Xenon Behavior in the MSRE ORNL-TM-3464 1971-10 txt
Estimated Cost of Adding a Third Salt-Circulation Loop for Controlling Tritium Migration in the 1000-MWe MSBR ORNL-TM-3428 1971-07 txt
ROD: A Nuclear and Fuel-cycle Analysis Code for Circulating-Fuel Reactors ORNL-TM-3359 1971-09 txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 10 ORNL-TM-3352 1972-12 txt
Experience with Sodium Fluoroborate Circulation in an MSRE-Scale Facility ORNL-TM-3344 1972-09 txt
Thermal Stability of Titanium-Modified Hastelloy-N at 650 and 760 C ORNL-TM-3321 1971-07 txt
Further Discussion of Instrumentation and Controls Development Needed for the MSBR ORNL-TM-3303 1971-08 txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 9 ORNL-TM-3259 1972-12 txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 8 ORNL-TM-3258 1972-05 txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 7 ORNL-TM-3257 1972-02-10 txt
MSRE Procedures for the Period Between Examination and Ultimate Disposal ORNL-TM-3253 1971-02 txt
Fluid Dynamic Studies of the MSRE Core ORNL-TM-3229 1970-11 txt
Molten-Salt Breeder Experiment Design Bases ORNL-TM-3177 1970-11 txt
A Study of Fission Products in the Molten-Salt Reactor Experiment by Gamma Spectrometry ORNL-TM-3151 1972-08 txt
Thermal Radiation Transfer of Afterheat in MSBR Heat Exchangers ORNL-TM-3145 1971-03 txt
Fluorine Production and Recombination in Frozen MSR Salts after Reactor Operation ORNL-TM-3144 1970-09 txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 6 ORNL-TM-3141 1971-12 txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 5 ORNL-TM-3140 1971-10 txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 4 ORNL-TM-3139 1971-08 txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 3 ORNL-TM-3138 1971-05 txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 2 ORNL-TM-3137 1971-02 txt
MSBR Control Studies: Analog Simulation Program ORNL-TM-3102 1971-05 txt
Influence of Ti, Zr, and Hf Additions on the Resistance of Modified Hastelloy-N to Irradiation Damage ORNL-TM-3064 1971-01 txt
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens - Fourth Group ORNL-TM-3063 1971-03 txt
Engineering Development Studies for Molten-Salt Breeder Reactor Processing No. 1 ORNL-TM-3053 1970-11 txt
MSRE Operator Training and Operating Techniques ORNL-TM-3041 1973-08 txt
MSRE Systems and Components Performance ORNL-TM-3039 1973-06 txt
Spray, Mist, Bubbles, and Foam in the MSRE ORNL-TM-3027 1970-06 txt
An Extended Hydraulic Model of the MSRE Circulating Fuel System ORNL-TM-3007 1970-06 txt
Reactor Power Measurement and Heat Transfer Performance in the MSRE ORNL-TM-3002 1970-05 txt
Quality-Assurance Practices in Construction and Maintenance of the MSRE ORNL-TM-2999 1970-04 txt
Experimental Dynamic Analysis of the MSRE with 233U Fuel ORNL-TM-2997 1970-04 txt
Development of Fuel- and Coolant-Salt Centrifugal Pumps for the MSRE ORNL-TM-2987 1970-10 txt
Compatibility of Fused Sodium Fluoroborate and BF3 Gas with Hastelloy-N Alloys ORNL-TM-2978 1970-06 txt
Plans for Post-Operation Examination of the MSRE ORNL-TM-2974 1970-04-07 txt
Calculated Radioactivity of MSRE Fuel Salt ORNL-TM-2970 1970-05 txt
A New Approach to a Design of Steam Generators for Molten Salt Reactor Power Plants ORNL-TM-2953 1971-06 txt
Parametric Survery of the Effects of Major Parameters of the Design of MSBR Heat Exchangers ORNL-TM-2952 1971-11 txt
Control Studies of a 1000-MWe MSBR ORNL-TM-2927 1970-05 txt
Tensile Properties of Hastelloy-N Welded After Irradiation ORNL-TM-2858 1970-04 txt
Frequency-Response Testing of the Molten-Salt Reactor Experiment ORNL-TM-2823 1970-03 txt
Computer Programs for MSBR Heat Exchangers ORNL-TM-2815 1971-04 txt
Preliminary Systems Design Description of the Salt Pump Test Stand for the MSBE ORNL-TM-2780 1969-12 txt
Design and Construction of Core Irradiation-Specimen Array for MSRE Runs 19 and 20 ORNL-TM-2743 1969-12 txt
Catastropic Corrosion of Type 304 Stainless Steel in a System Circulating Fused Sodium Fluoroborate ORNL-TM-2741 1970-01 txt
Mechanical Behavior of Artificial Graphites as Portrayed by Uniaxial Tests ORNL-TM-2727 1969-12 txt
Compatibility of Molybdenum-Base Alloy TZM with LiF-BeF2-ThF4-UF4 at 1100 C ORNL-TM-2724 1969-12 txt
Feasibility Study of Remote Cutting and Welding for Nuclear Plant Maintenance ORNL-TM-2712 1969-11 txt
Assessment of Molten Salts as LMFBR Intermediate Coolants ORNL-TM-2696 1969-09-03 txt
Inherent Neutron Source in MSRE with Clean 233U Fuel ORNL-TM-2685 1969-08 txt
Management of Noble-Gas Fission-Product Wastes from Reprocessing Spent Fuels ORNL-TM-2677 1969-11 txt
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens - Third Group ORNL-TM-2647 1970-01 txt
Conceptual System Design Description of the Salt Pump Test Stand for the MSBE ORNL-TM-2643 1969-08 txt
Fractional Crystallization Reactions in the System LiF-BeF2-ThF4 ORNL-TM-2596 1969-07-08 txt
Processing of the MSRE Flush and Fuel Salts ORNL-TM-2578 1969-08 txt
Theoretical Dynamic Analysis of the MSRE with 233U Fuel ORNL-TM-2571 1969-07 txt
Materials for Molten-Salt Reactors ORNL-TM-2511 1969-05 txt
Compatibility of Hastelloy-N and Croloy-9M with NaBF4-NaF-KBF4 Fluoroborate Salt ORNL-TM-2490 1969-04 txt
MSBR Control Studies ORNL-TM-2489 1969-06-02 txt
Extraction of U, Th, and Rare Earths from Molten LiF-BeF2 into Liquid Li-Bi Solutions ORNL-TM-2486 1969-03 txt
Pre- and Post-Irradiation Mechanical Properties of Hastelloy-N Welds ORNL-TM-2483 1969-03 txt
Design, Construction, and Testing of a Large Molten Salt Filter ORNL-TM-2478 1969-03 txt
Dynamic Analysis of a Salt Supercritical Water Heat Exchanger and Throttle used with MSRE ORNL-TM-2405 1969-01 txt
Diffusion of Titanium in Modified Hastelloy-N ORNL-TM-2392 1969-01 txt
Bubbles, Drops, and Entrainment in Molten Salts ORNL-TM-2373 1968-12 txt
The Language of Nuclear Science ORNL-TM-2367 1968-09-17 txt
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens - Second Group ORNL-TM-2359 1969-02 txt
Solubility of Cerium Trifluoride in Molten Mixtures of LiF, BeF2, and ThF4 ORNL-TM-2335 1969-01 txt
Determination of the Void Fraction in the MSRE Using Small Induced Pressure Perturbations ORNL-TM-2318 1969-02-06 txt
Physical Properties of Molten-Salt Reactor Fuel, Coolant, and Flush Salts ORNL-TM-2316 1968-08 txt
Measurement of Helium Void Fraction in the MSRE Fuel Salt using Neutron-Noise Analysis ORNL-TM-2315 1968-08-27 txt
Postirradiation Tensile and Creep-Rupture Properties of Incoloy 800 at 700 and 760 C ORNL-TM-2305 1968-12 txt
MSRE Design and Operations Report Part XI-A: Test Program for 233U Operations ORNL-TM-2304 1968-09 txt
Preliminary Study of a Molten-Salt Burst Reactor ORNL-TM-2282 1968-07-10 txt
Irradiation Behavior of Cladding and Structural Materials ORNL-TM-2258 1968-09 txt
Chemical Feasibility of Fueling Molten-Salt Reactors with PuF3 ORNL-TM-2256 1968-06-20 txt
Removal of 135Xe from Circulating Fuel Salt of the MSBR by Mass Transfer to Helium Bubbles ORNL-TM-2245 1968-07-23 txt
Proton Reaction Analysis for Lithium and Fluorine in Graphite using a Slit-Scanning Technique ORNL-TM-2238 1968-07 txt
Design of an Engineering-Scale, Vacuum Distillation Experiment for MSR Fuel ORNL-TM-2213 1968-11 txt
Electrical Conductivity of Molten Fluorides: A Review ORNL-TM-2180 1968-03-26 txt
Fluoride Volatility for Recovering U and Pu from Spent UO2 Fuels ORNL-TM-2170 1969-04 txt
Graphite Behavior and its Effects on MSBR Performance ORNL-TM-2136 1969-02 txt
MSRE Design and Operations Part Report V-A: Safety Analysis of Operation with 233U ORNL-TM-2111 1968-02 txt
Tube Vibration in MSRE Primary Heat Exchanger ORNL-TM-2098 1968-01-03 txt
Measurement of Relative Volatilities of Rare-Earth Fluorides in Mixtures of LiF and BeF2 ORNL-TM-2058 1968-01 txt
Containers for Molten Fluoride Spectroscopy ORNL-TM-2047 1967-11-08 txt
Effects of Irradiation on the Mechanical Properties of Hastelloy N ORNL-TM-2043 1968-01 txt
Reduction of Iron Dissolved in Molten LiF-ThF4 ORNL-TM-2036 1967-11-02 txt
Closed-Circuit Television Viewing in Maintenance of Radioactive Systems at ORNL ORNL-TM-2032 1967-11-01 txt
Investigation of One Concept of a Thermal Shield for the Room Housing an MSBR ORNL-TM-2029 1967-11 txt
Corrosion Behavior of Nickel-Molybdenum Alloys in Fused Fluoride Mixtures ORNL-TM-2021 1967-05 txt
An Evaluation of the MSRE Hastelloy-N Surveillance Specimens - First Group ORNL-TM-1997 1967-11 txt
Experience with Hi-Temp Centrifugal Pumps and their Application to MSBRs ORNL-TM-1993 1967-09 txt
A Literature Survey of the Fluorides and Oxyfluorides of Molybdenum ORNL-TM-1976 1967-10 txt
Operation of Molten-Salt Convection Loops in the ORR ORNL-TM-1960 1967-12 txt
Review of Molten-Salt Reactor Physics Calculations ORNL-TM-1946 1967-08 txt
"MATEXP", A Program for Solving ODEs by the Matrix Exponential Method ORNL-TM-1933 1967-08-30 txt
Corrosion of the Volatility Pilot Plant INOR-8 Dissolver ORNL-TM-1907 1967-07-21 txt
In- and Ex-Reactor Stress-Rupture Properties of Hastelloy N Tubing ORNL-TM-1906 1967-09 txt
Maintenance Development Program for MSBRs ORNL-TM-1859 1967-06-30 txt
Safety Program for MSBRs ORNL-TM-1858 1967-06-09 txt
Physics Program for MSBRs ORNL-TM-1857 1967-06-12 txt
Instrumentation and Controls Development for MSBRs ORNL-TM-1856 1967-05-22 txt
Components and Systems Development for MSBRs ORNL-TM-1855 1967-06-30 txt
Materials Development for MSBRs ORNL-TM-1854 1967-06 txt
Chemical Research and Development for MSBRs ORNL-TM-1853 1967-06-06 txt
Fuel and Blanket Processing Development for MSBRs ORNL-TM-1852 1967-06 txt
Summary of the Objectives, Design, and a Program of Development of MSBRs ORNL-TM-1851 1967-06-12 txt
A Model for Computing the Migration of Very Short-Lived Noble Gases into MSRE Graphite ORNL-TM-1810 1967-07 txt
The Reactivity Balance in the MSRE ORNL-TM-1796 1967-03-10 txt
Considerations of Low-Pressure Distillation of MSBR Fuels ORNL-TM-1730 1967-03 txt
Experimental Dynamic Analysis of the MSRE ORNL-TM-1647 1966-10-13 txt
Period Measurements on the MSRE During Fuel Circulation: Theory and Experiment ORNL-TM-1626 1966-10 txt
Tests of Various Particle Filters for Removal of Oil Mists and Hydrocarbon Vapor ORNL-TM-1623 1966-09-07 txt
Design Study of a Heat-Exchange System for One MSBR Concept ORNL-TM-1545 1967-09 txt
Solutions to the Problems of High-Temperature Irradiation Embrittlement ORNL-TM-1544 1966-06 txt
Removal of Protactinium from Molten Fluoride Breeder Blanket Mixtures ORNL-TM-1543 1966-06-01 txt
Summary of Molten-Salt Breeder Reactor Design Studies ORNL-TM-1467 1966-03-24 txt
Simulators for Training MSRE Operators ORNL-TM-1445 1966-04-05 txt
A Study of Lead and Lead-Salt Corrosion in Thermal-Convection Loops ORNL-TM-1437 1966-04 txt
The Welding of New Solution-Strengthened Nickel-Base Alloys ORNL-TM-1408 1966-04 txt
Studies of the Carbon Distribution in Hastelloy-N ORNL-TM-1353 1966-02 txt
Elevated-Temperature Mechanical Properties of Welds in a Ni-Mo-Cr-Fe Alloy ORNL-TM-1341 1966-01 txt
A Technique for Calculating Frequency Response and its Sensitivity to Parameter Changes ORNL-TM-1189 1965-06-24 txt
Production of a Low-Boron Heat of Hastelloy N ORNL-TM-1146 1965-06-11 txt
Oxide Chemistry and Thermodynamics of Molten LiF-BeF2 by Equilibriation with Gaseous H2O-HF Mixtures ORNL-TM-1129 1965-05-07 txt
Stability Analysis of the MSRE ORNL-TM-1070 1965-12 txt
Molten-Salt Converter Reactor: Design Study and Power Cost Estimates for a 1000 MWe Station ORNL-TM-1060 1965-09 txt
Reconstitution of MSR Fuel by Reducing UF6 Gas to UF4 in a Molten Salt ORNL-TM-1051 1965-03-11 txt
Tube Plugging in the MSRE Primary Heat Exchanger ORNL-TM-1023 1965-02 txt
Tensile and Creep Properties of INOR-8 for the MSRE ORNL-TM-1017 1965-02 txt
Effect of Elevated Temperature Irradiation on the Strength and Ductility of Hastelloy-N ORNL-TM-1005 1965-02 txt
MSRE Neutron Source Requirements ORNL-TM-0935 1964-09-11 txt
MSRE Design and Operations Report Part XI: Test Program ORNL-TM-0911 1965-01 txt
MSRE Design and Operations Report Part X: Maintenance Equipment and Procedures ORNL-TM-0910 1965-01 txt
MSRE Design and Operations Report Part IX: Safety Procedures and Emergency Plans ORNL-TM-0909 1965-01 txt
MSRE Design and Operations Report Part VIII: Operating Procedures (Volume I) ORNL-TM-0908A 1966-01 txt
MSRE Design and Operations Report Part VIII: Operating Procedures (Volume II) ORNL-TM-0908B 1966-01 txt
MSRE Design and Operations Report Part VII: Fuel Handling and Processing Plant (revision) ORNL-TM-0907REV 1968-12-28 txt
MSRE Design and Operations Report Part VII: Fuel Handling and Processing Plant ORNL-TM-0907 1965-01 txt
Effect of Irradiation on the Bend Transition Temperatures of Mo- and Nb-Base Alloys ORNL-TM-0880 1964-07 txt
MSRE Design and Operations Report Part VI: Operating Limits (Revision 3) ORNL-TM-0733REV3 1969-07-25 txt
MSRE Design and Operations Report Part VI: Operating Limits (Revision 2) ORNL-TM-0733REV2 1966-09-19 txt
MSRE Design and Operations Report Part VI: Operating Limits (Revision) ORNL-TM-0733REV 1965-08-03 txt
MSRE Design and Operations Report Part VI: Operating Limits ORNL-TM-0733 1965-01 txt
MSRE Design and Operations Report Part V: Reactor Safety Analysis Report ORNL-TM-0732 1965-01 txt
MSRE Design and Operations Report Part III: Nuclear Analysis ORNL-TM-0730 1965-01 txt
MSRE Design and Operations Report Part IIB: Nuclear and Process Instrumentation ORNL-TM-0729B 1965-01 txt
MSRE Design and Operations Report Part IIA: Nuclear and Process Instrumentation ORNL-TM-0729A 1965-01 txt
MSRE Design and Operations Report Part I: Description of Reactor Design ORNL-TM-0728 1965-01 txt
Inherent Neutron Sources in Clean MSRE Fuel Salt ORNL-TM-0611 1963-08-27 txt
Mechanical Properties of INOR-8 Cast Metal ORNL-TM-0607 1963-08-06 txt
Design and Operation of Forced-Circulation Corrosion Testing Loops with Molten Salt ORNL-TM-0528 1963-05-01 txt
Design Studies and Cost Estimates of Two Fluoride Volatility Plants ORNL-TM-0522 1962-10-10 txt
MSRE Maintenance Proposal ORNL-TM-0519 1963-03-14 txt
Radiation Chemistry of MSR System ORNL-TM-0500 1963-03-13 txt
Analysis of Filling Accidents in MSRE ORNL-TM-0497 1966-08-16 txt
Some Chemical Aspects of Molten-Salt Reactor Safety ORNL-TM-0458 1962-12-14 txt
Corrosion of Nickel-Base Specimens Exposed in the Volatility Pilot Plant Mark III Fluorinator ORNL-TM-0411 1963-01-04 txt
Prediction of Effective Yields of Delayed Neutrons in MSRE ORNL-TM-0380 1962-10-13 txt
Temperature and Reactivity Coefficient Averaging in the MSRE ORNL-TM-0379 1962-10-15 txt
Temperatures in the MSRE Core During Steady-State Power Operations ORNL-TM-0378 1962-11-05 txt
Corrosion Behavior of Reactor Materials in Fluoride Salt Mixtures ORNL-TM-0328 1962-09-19 txt
Influence of Various Gaseous Environments on the Creep-Rupture Properties of Nuclear Materials for Hi-Temp Service ORNL-TM-0326 1962-09-19 txt
Homogenization of MSRP Fuel Samples ORNL-TM-0291 1962-07-05 txt
576 MWt Natural Convection Molten-Salt Reactor Study ORNL-TM-0269 1962-07-05 txt
Experimental 5 MW Thermal Convection Molten-Salt Reactor ORNL-TM-0268 1962-07-05 txt
Xenon Diffusion in Graphite in Molten-Salt Reactors ORNL-TM-0262 1962-06-27 txt
Safety Calculations for MSRE ORNL-TM-0251 1962-05-15 txt
MURGATROYD--An IBM 7090 Program for the Analysis of the Kinetics of the MSRE ORNL-TM-0203 1962-04-06 txt
Corrosion Behavior of Nickel-Molybdenum Alloys in Fused Fluoride Mixtures ORNL-TM-0202 1969-05 txt
Development of Freeze Valve for Use in the MSRE ORNL-TM-0128 1962-02-28 txt
Laboratory-Scale Demonstration of the Fused Salt Volatility Process ORNL-TM-0080 1961-12-06 txt
Water Test Development of the Fuel Pump for the MSRE ORNL-TM-0079 1962-03-27 txt
Thermal-Stress and Strain-Fatigue Analyses of the MSRE Fuel and Coolant Pump Tanks ORNL-TM-0078 1962-10-03 txt
Catastropic Oxidation of High-Temperature Alloys ORNL-TM-0051 1961-11-10 txt
Carbon-14 Production in Nuclear Reactors ORNL-NUREG-TM-12 1977-02 txt
Removal of Tritium from MSBR Fuel ORNL-MIT-117 1970-11-18 txt
Analysis and Scaleup of the Pulsed-Gas Impregnation of Graphite with Carbon ORNL-MIT-99 1970-03-05 txt

ORNL Central Files Related to the Molten-Salt Reactor Program

report filename date ocr
Decommissioning Study for the MSRE ORNL-CF-77-391 1977-08-25 txt
Consideration of Possible Methods of Disposal of MSRE Salts ORNL-CF-72-1-1 1972-01-28 txt
Review of Possible Choices of Secondary Coolants for MSRs ORNL-CF-71-8-10 1971-08-06 txt
Additional Calculations of the Distribution of Tritium in the MSRE ORNL-CF-71-7-8 1971-07-07 txt
Plans for the MSRE during the Period Between Examination and Ultimate Disposal ORNL-CF-70-10-14 1970-10-09 txt
Critique of the MSRE: A Collection of Comments Submitted by Persons Associated with the Reactor ORNL-CF-70-9-3 1970-09-01 txt
Calculation of Stresses During a Thermal Transient in an MSBR Outlet Nozzle ORNL-CF-70-3-2 1970-03-02 txt
Tritium in the MSRE: Calculated Production Rates and Observed Amounts ORNL-CF-70-2-7 1970-02-04 txt
Graphite for Molten-Salt Reactors ORNL-CF-68-11-18 1968-11-12 txt
Performance of MSRE Nuclear Power Control Systems ORNL-CF-68-5-11 1968-05-01 txt
Decay Heat Generation by Fission Products and 233Pa in a Single-Region MSR ORNL-CF-68-3-38 1968-03-25 txt
Protactinium Removal from MSBR Fertile Salt ORNL-CF-68-1-42 1968-01-24 txt
The Program Planned for the Molten-Salt Reactor Experiment ORNL-CF-67-8-10 1967-08-01 txt
Analysis of MSRE Zero-Power Flux Noise Using Digital Techniques ORNL-CF-66-2-67 1966-02-11 txt
Results of Neutron Fluctuation Measurements Made During the MSRE Zero-Power Experiment ORNL-CF-65-10-18 1965-10-29 txt
Preliminary Report on Results of MSRE Zero-Power Experiments ORNL-CF-65-8-32 1965-08-16 txt
Comparison of Calculations and Uncertainties in the Temperature Coefficients of Reactivity in the MSRE ORNL-CF-65-3-1 1965-03-03 txt
A Literature Survey of Thermal and Physical Properties of Molten Fluoride and Chloride Salt Mixtures ORNL-CF-63-9-20 1963-09-04 txt
Modifications to Specifications for MSRE Graphite ORNL-CF-63-2-18 1963-02-14 txt
Preliminary Equations to Describe Iodine and Xenon Behavior in the MSRE ORNL-CF-62-11-69 1962-11-12 txt
MSRE Analog Computer Simulation of the System with a Servo Controller ORNL-CF-61-12-50 1961-12-26 txt
Delayed Neutron Losses in Circulating Fuel Reactors ORNL-CF-61-10-39 1961-10-11 txt
Thorium Breeder Reactor Evaluation Part I: Fuel Yields and Cost of a MSBR ORNL-CF-61-8-86 1961-08-18 txt
MSRE Preliminary Physics Report ORNL-CF-61-4-62 1961-04-19 txt
MSRE Preliminary Priliminary Hazards Report ORNL-CF-61-2-46 1961-02-28 txt
Homogeneous Molten-Salt Reactors ORNL-CF-60-12-111 1960-12-13 txt
MSRE Radiator Design ORNL-CF-60-11-108 1960-11-30 txt
MSRE Analog Computer Simulation of a Loss-of-Flow Accident in the Secondary System ORNL-CF-60-11-20 1960-11-04 txt
Molten Salt Reactors: Report for 1960 Ten-Year-Plan Evaluation ORNL-CF-60-6-97 1960-06-28 txt
Interim Report on Fluid-Fuel Thermal Breeder Reactors ORNL-CF-60-3-31 1960-03-15 txt
Molten-Salt Breeder Reactors ORNL-CF-59-12-64 1960-01-12 txt
Molten Salt-Graphite Compatibility Test Results ORNL-CF-59-8-133 1959-08-31 txt
Processing of Molten Salt Power Reactor Fuel ORNL-CF-59-2-61 1959-04-01 txt
Preliminary Study of a Graphite-Moderated Molten-Salt Power Reactor ORNL-CF-59-1-26 1959-01-13 txt
Fuel Cycle Costs in a Graphite-Moderated Slightly-Enriched Fused-Salt Reactor ORNL-CF-59-1-13 1959-02-24 txt
The Need for U-233 Breeding ORNL-CF-58-12-79 1958-12-15 txt
Survey of Low-Enrichment Molten-Salt Reactors ORNL-CF-58-10-60 1958-10-17 txt
U233 Breeders--Commentary and General Remarks ORNL-CF-58-10-37 1958-10-08 txt
Screening Tests of Mechanical Pipe Joints for a Fused Salt Reactor System ORNL-CF-58-8-33 1958-08-13 txt
A Molten-Salt Natural Convection Reactor System ORNL-CF-58-2-46 1958-02-05 txt
Molten Salt Heat Transfer ORNL-CF-58-2-40 1958-02-18 txt
Declassification of Molten Salt Reactors ORNL-CF-57-12-29 1957-12-02 txt
Molten Salts for Civilian Power ORNL-CF-57-10-41 1957-10-10 txt
ORSORT Study: High Performance Marine Reactor ORNL-CF-57-8-7 1957-08 txt
Molten Fluoride Reactors ORNL-CF-57-6-69 1957-05 txt
Maintenance of Various Reactor Types ORNL-CF-57-4-92 1957-04-08 txt
A Preliminary Study of Molten-Salt Power Reactors ORNL-CF-57-4-27 1957-12-03 txt
Fused Salt Power Reactor Study: Discussion Meeting 8 ORNL-CF-57-3-31 1957-03-08 txt
Fused Salt Power Reactor Study: Discussion Meeting 7 ORNL-CF-57-2-65 1957-02-14 txt
Fused Salt Power Reactor Study: Discussion Meeting 6 ORNL-CF-57-1-135 1957-01-30 txt
Power Reactor Based on Fused Salt Technology ORNL-CF-57-1-57 1957-01-17 txt
Fused Salt Power Reactor Study: Discussion Meeting 5 ORNL-CF-56-12-101 1956-12-29 txt
Fused Salt Power Reactor Study: Discussion Meeting 4 ORNL-CF-56-12-35 1956-12-11 txt
Fused Salt Power Reactor Study: Discussion Meeting 3 ORNL-CF-56-10-110 1956-10-29 txt
Proposal for Fused Salt Power Reactor Study Group ORNL-CF-56-9-107 1956-09-26 document missing
Fused Salt Power Reactor Study: Discussion Meeting 2 ORNL-CF-56-9-32 1956-09-11 txt
ORSORT Study: 600 MW Fused Salt Homogeneous Reactor Power Plant ORNL-CF-56-8-208 1956-08 txt
ORSORT Study: Fused Salt Fast Breeder ORNL-CF-56-8-204 1956-08 txt
Fused Salt Power Reactor Study: Discussion Meeting 1 ORNL-CF-56-7-114 1956-07-18 txt
Fused Salt Heat Transfer ORNL-CF-56-5-65 1956-05-14 document missing
Molten Salt Requirements for Pratt and Whitney Aircraft ORNL-CF-56-4-173 1956-04-26 txt
Feasibility of Molten Salt Power Reactors ORNL-CF-56-3-117 1956-03-23 document missing
Fused Salt Processing: Problem Statement ORNL-CF-56-2-80 1956-02-17 txt
ORSORT Study: Circulating Fluoride Reactor for a Submarine ORNL-CF-53 1953-08-20 document missing
ORSORT Study: Fused Salt Breeder Reactor ORNL-CF-53-10-25 1953 document missing
ORSORT Study: Reflector-Moderated, Circulating Fuel Aircraft Reactor ORNL-CF-53-9-84 1953-08-14 txt

Liquid-Chloride Reactors

report filename date ocr
Cursory First Look at the Molten Chloride Fast Reactor as an Alternative to the Conventional BATR Concept MCFR_BATR 1992-04 txt
Configuration of a Molten Chloride Fast Reactor on a Thorium Fuel Cycle to Current Nuclear Fuel Cycle Concerns MCFR_UCLA_Ottewitte_thesis 1982 txt
Molten Plutonium Chloride Fast Breeder Reactor Cooled by Molten Uranium Chloride ANSE-1-277 1974 txt
New Boiling Salt Fast Breeder Reactor Concepts NED-5-109 1967 txt
Fuel Properties and Nuclear Performance of Fast Reactors Fueled with Molten Chlorides NA-3-540 1967 txt
Fission Product Effects in Molten Chloride Fast-Reactor Fuels NSE-23-189 1965 txt
Molten-Salt Fast Reactors ANL-6792 1963-10 txt
Thermodynamic Stability of Metals and Their Chlorides in the Presence of UCl3 and PuCl3 MSR-63-53 1963-10-31 txt
Chemical Problems of Non-Aqueous Fluid-Fuel Reactors MIT-5001 1952-10-15 txt
Nuclear Problems of Non-Aqueous Fluid-Fuel Reactors MIT-5000 1952-10-15 txt
An Assessment of a 2500 MWe Molten Chloride Salt Fast Reactor AEEW-R956 1974-08 txt

EIR Reports

report filename date ocr
Molten Chlorides Fast Breeder Reactor Problems and Possibilities EIR-215 1972-06 txt
Molten Chlorides Fast Breeder Reactor Physics Calculations EIR-229 1972-11 txt
High Temperature Reaction of Uranium Carbides and Transient Metal Chlorides in Molten Chloride Media EIR-238 1973-06 txt
A Molten Salt Fast Thermal Reactor System with no Waste EIR-249 1974-01 txt
Thorium, Uranium, other Metals and Materials from Earth's Crust Rocks EIR-252 1974-04 txt
The Possibility of Continuous In-core Gaseous Extraction of Volatile Fission Products in a Molten Fuel Reactor EIR-257 1974-05 txt
A High-Flux Fast Molten Salt Reactor for the Transmutation of 137Ce and 90Sr EIR-259 1975-09 txt
Salzschmelze-Reaktorentagung in Fontenay-aux-Roses / Salt smelter reactor conference in Fontenay-aux-Roses EIR-266 1974-10 txt
Chemical State of Sulphur Obtained by the 35Cl(n,p)35S Reaction During In-Pile Irradiation EIR-267 1974-12 txt
Transmutation of Fission Products in a Liquid-Fuelled Fast Fission Reactor with Thermal Column EIR-270 1975-02 txt
Breeding in Molten-Salt Reactors EIR-276 1976-04 txt
Fast Reactors Using Molten Chloride Salts as Fuel: Final Report (1972-1977) EIR-332 1978-01 txt
Reactor with Very Low Fission Product Inventory EIR-411 1980-07 txt
Thermische Salzschmelzebrilter in Frankreich / Thermal molten salt filters in France EIR-AN-HL-230 1975-06 txt
Information über die Anwendungsmöglichkeiten von Salzschmelzen in der Energiewirtschaft / Information about possible applications of salt melts in the energy industry EIR-AN-HL-234 1975-08 txt
Kontrollblatt für externe Publikationen und Vorträge / Control sheet for external publications and lectures EIR-AW-GL-335 1978-09 txt
Salzschmelzespeicher anstatt Hydropumpenspeicher für die Speicherung der elektrischen Energie / Molten salt storage instead of hydraulic pump storage for storing electrical energy EIR-TM-HL-233 1974-08 txt
Synthesis and Gas Chromatography of Selected Metal Chlorides EIR-TM-HL-235 1974-09 txt
Hochtemperatur-Wärmespeicher mit Salzschmelze und intermediärem Gaskreislauf / High-temperature heat accumulator with molten salt and intermediate gas cycle EIR-TM-HL-238 1974-08 txt
Titrimetrische Pu-Bestimmung unter Verwendung von Cu(I)-Chlorid als Reduktionsmittel / Titrimetric Pu determination using Cu(I) chloride as reducing agent EIR-TM-HL-255 1975-04 txt
Very high breeding ratio in the molten chloride fast power reactor with external cooling EIR-TM-HL-261 1975-07 txt

Assorted Documents

report filename date ocr
ORNL Review Volume 3, Number 2 - Fall 1969 ORNL-Review-v3n2 1969 txt
ORNL Review Volume 10, Number 4 - Fall 1969 ORNL-Review-v10n4 1977 txt
MSR Concepts with Reduced Potential for Proliferation of Special Nuclear Materials ORAU-IEA-77-13 1977 txt
Catalog of Nuclear Reactor Concepts: Part I, Section III ANL-7092 1965-09 txt
Parametric Survey of Criticality-Limited Fast Reactors Employing Uranium Fluoride Fuels JPL-TR-32-198 1962-03-15 txt
An Evaluation of the Molten Salt Breeder Reactor WASH-1222 1972-09 txt
Updated (1970) Cost-Benefit Analysis of the US Breeder Reactor Program WASH-1184 1972-01 txt
Cost-Benefit Analysis of the US Breeder Reactor Program WASH-1126 1969-04 txt
The Use of Thorium in Nuclear Power Reactors WASH-1097 1969-06 txt
Ebasco Services 1000 MWe MSBR Conceptual Design Study TID-26156 1972-02 txt
Sargent and Lundy Capital Cost Evaluation of 1000 MWe MSCR Power Plants SL-1954 1962-06 txt
Report of the Fluid Fuel Reactors Task Force TID-8507 1959-02 txt
Lithium Separation by Electrolysis LA-1156 1950-09 txt
The Radiochemistry of Uranium, Neptunium, and Plutonium--An Updating NAS-NS-3063 1986-02 txt
The Radiochemistry of Neptunium NAS-NS-3060 1974-12 txt
The Radiochemistry of Plutonium NAS-NS-3058 1965-09 txt
The Radiochemistry of Uranium NAS-NS-3050 1962-03 txt
The Radiochemistry of the Rare Gases NAS-NS-3025 1960-10 txt
The Radiochemistry of Protactinium NAS-NS-3016 1959-12 txt
The Radiochemistry of Beryllium NAS-NS-3013 1960-05 txt
The Radiochemistry of Thorium NAS-NS-3004 1960-01 txt
Catalog of Nuclear Reactor Concepts: Part I. Homogeneous and Quasi-Homogeneous Reactors - Secition I. Particulate-Fueled Reactors ANL-6892 1964-05 txt
Catalog of Nuclear Reactor Concepts: Part I. Homogeneous and Quasi-Homogeneous Reactors - Secition II. Reactors Fueled with Homogeneous Aqueous Solutions and Slurries ANL-6909 1964-07 txt
Catalog of Nuclear Reactor Concepts: Part I. Homogeneous and Quasi-Homogeneous Reactors - Secition III. Reactors Fueled with Liquid Metals ANL-7138 1966-01 txt
Catalog of Nuclear Reactor Concepts: Part I. Homogeneous and Quasi-Homogeneous Reactors - Secition V. Reactors Fueled with Uranium Hexafluoride, Gasses, or Plasmas ANL-7180 1966-03 txt
Catalog of Nuclear Reactor Concepts: Part I. Homogeneous and Quasi-Homogeneous Reactors - Secition VI. Solid Homogeneous (Semihomogeneous) Reactors ANL-7228 1966-06 txt
Hydroxides as Moderator Coolants in Power-Breeder-Reactors BMI-746 1952-05 txt
Task I Final Report - Design Studies of Steam Generator for Molten Salt Reactors ND-74-66 1975-01 txt
Nuclear Metallurgy, Volume 15, Symposium on Reprocessing of Nuclear Fuels NSA-23-038023 1969-08 txt
Design Concepts for the Core Structure of a MOSEL (MOlten Salt ExperimentaL) Reactor NSE-1965 1965-06 txt
Physical Properties Data Compilations Relevant to Energy Storage - IV. Molten Salts: Data on Additional Single and Multi-Component Salt Systems NSRDS-NBS-61-p4 1988-08 txt
Aspects of Molten Fluorides as Heat Transfer Agents for Power Generation P1152-2038 1979-02 txt
Fusion-Fission Energy Systems Evaluation PNL-3116 1980-01 txt

New Piles Commitee

report filename date ocr
Notes on Meeting of April 26, 1944 MUC-LAO-17 1944-04 txt
Notes on Meeting of April 28, 1944 MUC-LAO-18 1944-04 txt
Notes on Meeting of May 5, 1944 MUC-LAO-19 1944-05 txt
Notes on Meeting of May 10, 1944 MUC-LAO-20 1944-05 txt
Notes on Meeting of May 12, 1944 MUC-LAO-21 1944-05 txt
Notes on Meeting of July 6, 1944 MUC-LAO-30 1944-07 txt
Notes on Meeting of July 14, 1944 MUC-LAO-40 1944-07 txt
Notes on Meeting of July 26, 1944 MUC-LAO-41 1944-07 txt