Oak Ridge National Lab - MSR Documentation
An Assessment Of A 2500 MWe MOLTEN
Molten Plutonium Chloride Fast Breeder
Molten-Salt Fast Reactors
Catalog Of Nuclear Reactor Concepts
A Reflector Moderated, Circulating Fuel, Aircraft Reactor
Fused Salt Fast Breeder Reactor Design Ans Feasibility Study
Maintenance of Various Reactor Types
Reactor Design And Fesibility Study High Performance Marine Reactor
Molten salt For Civilian Power
Unclassification Of Molten Salt Reactors
A Molten Salt Natural Convection Reactor System
U235 Breeders - Comentary And General remarks
Survey Of Low Enrichment Molten-Salt Reactors
The Need For U235 Breeding
Fuel Cycle Costs In A Graphite Modulated Slightly Enriched Fused Salt Reactor
A Preliminary Study Of A Graphite Moderated Molten salt Power Reactor
Prosessing Of Molten Salt Power Reactor Fuel
Molten Salt-Graphite CompatibilityTest, results Of Physical And Chemical Measurements
Molten-Salt Breeder Reactors
MSRE Reactor Design
Homogeneous Molten Salt Reactors
MSRE Preliminary Physics Report
Thorium Breeder Reactor Evalution - Part 1
A Molten Salt fast Thermal Reactor Sytem With No Waste
The Possibility Of Continuous In-Core Extraction Of Volatile Fission Products In A Molten Fuel Reactor
A High-Flux Molten Salt Reactor For The Transmutation Of Caesium-137 And Strontium-90
Chemical State OF Sulphur By The 35Cl(n,p)35S Reaction During In Pile Irradiation
The Transmutation Of Fission Products (Cs-137 , Sr-90) In A Liquid Fuelled Fast Fission Reactor With Thermal Column
Fast Reactors Using Molten chloride Salts As Fuel
Reactor With very Low Fission Product Inventory
Fission-Product Effects In molten Chloride Fast-reactor Fuels
Thorium Based Fuel Options For Generation Of Electricity: Developments In The 1990's
Thorium Fiuel Cycle - Potential Benefits And Challenges
An Advanced Molten Salt Reactor Using High-Temperature Reactor Technology
A Parametric Survey Of Criticality-Limited Fast Reactors Employing Uranium Fluoride Fuels
Lithium Isotope Seperation By Electrolysis
Cursory First look At The Molten Chloride Fast Reactor As An Alternative To The Conventional BATR Concept
Configuration Of A Molten Chloride Reactor On A Thorium Fuel cycle To Current Nuclear Fuel Cycle Concerns
Nuclear Problems Of Non-Aqueous Fluid-Fuel Reactors
Chemical Problems Of Non-Aqueuous Fluid -Fuel Reactors
Reactors with molten salts: options And Missions
Thr Molten Salt Reactor Adventure
The Molten Salt Reactor Option For Beneficial Use Of Fissile Material From Dismanted weapons
Thermodynamic Stability Of Metals And Their Chlorides In The Presence Of UCl3 and PuCl3
Chapter X. MSR-FUJI General Information, Technical Features, and Operating
Fuel Properties And Nuclear Performance Of Fast Reactors Fueled With Molten Chlorides
The Radiochemistry Of Thorium
THe Radiochemistry Of Beryllium
The Radiochemistry Of Protactinium
The Radiochemistry Of Protactinium
The Radiochemistry Of Uranium
The Radiochemistry Of Plutonium
The Radiochemistry Of Neptunium
The Radiochemistry Of Uranium, Neptunium And Plutonium - An Updating
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
Engineering Development Of The MSBR Fuel Recycle
Therical Dynamics Analysis Of The Molten-Salt Reactor Experiment
Experiences With Dynamic Testing Methods At The Molten-Salt Reactor experiment
Experience With The Molten-Salt Reactor Experiment
Molten-Salt Reactors - History, status And Potemtial
New Developments In Materials For Molten-Salt Reactors
Preface: Molten-Salt Reactors
The Aircraft Reactor Experiment - Design And Construction
The Aircraft Reactor Experiment - Operation
The Aircraft Reactor Experiment - Physics
Molten Fluorides As Power Reactor Fuels
Molten-Salt Reactor Concepts With reduced Potential Fort Proliferation Of Special Nuclear Materials
The Aircrsft Nuclear Propulsion Program And General Reactor Technology
Aircraft Nuclear Propulsion Project Quarterly Progress Report - Sept 10, 1951
Aircraft Nuclear Propulsion Project Quarterly Progress Report - Dec 10, 1951
Aircraft Nuclear Propulsion Project Quarterly Progress Report - March 10, 1952
Aircraft Nuclear Propulsion Project Quarterly Progress Report - June 10, 1952
Aircraft Nuclear Propulsion Project Quarterly Progress Report - Sept 10, 1952
Aircraft Nuclear Propulsion Project Quarterly Progress Report - Dec 10, 1952
General Information Concerning Hydroxides
Aircraft Nuclear Propulsion Project Quarterly Progress Report - March 10, 1953
Aircraft Nuclear Propulsion Project Quarterly Progress Report - June 10, 1953
Aircraft Nuclear Propulsion Project Quarterly Progress Report - Sept 10, 1953
Aircraft Nuclear Propulsion Project Quarterly Progress Report - Dec 10, 1953
Aircraft Nuclear Propulsion Project Quarterly Progress Report - Dec 10, 1953
ORNL Aircaft Nuclear Power Plant Designs
Aircraft Nuclear Propulsion Project Quarterly Progress Report - June 10, 1954
Aircraft Nuclear Propulsion Project Quarterly Progress Report - Sept 10, 1954
Fused Salt Heat Transfer PartII: Forced Convection Heat Transfer In circulating Tubes Containing NaF-KF-LiF Eutectic
Aircraft Nuclear Propulsion Project Quarterly Progress Report - Dec 10, 1954
Aircraft Reactor Test Hazards Summary Report
Aircraft Nuclear Propulsion Project Quarterly Progress Report - June 10, 1955
Aircraft Nuclear Propulsion Project Quarterly Progress Report - Sept 10, 1955
Operation Of The Aircraft Reactor Experiment
Corrosion Of Materials In Fused Hydroxides
Design Report Of The Aircraft Reactor Test
Aircraft Nuclear Propulsion Project Quarterly Progress Report - June 10, 1956
Aircraft Nuclear Propulsion Project Quarterly Progress Report - Sept 10, 1956
Aircraft Nuclear Propulsion Project Quarterly Progress Report: Sept 30, 1957
Guide To The Phase Diagrams Of The Fluoride Systems
Molten-Salt Reactor Program Quarterly Progress Report: Oct 31, 1957
Molten-Salt Reactor Program Quarterly Progress Report: Jan 31, 1958
Solubility And Stability Of PuF3 In Fused Alkali Fluoride-Beryllium Fluoride Mixtures
Phase Diagrams Of Nuclear Materials
Molten-Salt Reactor Program Quarterly Progress Report: June 31, 1958
Gas Cooled, Molten Salt Heat Exchanger - Design Study
Molten-Salt Reactor Program Quarterly Progress Report: Oct 31, 1958
Molten-Salt Reactor Program Status Report
Measurements Through A Hot Cell Window Using Optical Tooling
The Fused Salt-Fluoride Volatility Process For recovering Uranium
Aluminum Chloride As A Thermodynamic Working Fluid And Heat Transfer Medium
Molten-Salt Reactor Program Quarterly Progress Report: Jan 31, 1957
Molten-Salt Reactor Program Quarterly Progress Report: April 30, 1959
Nuclear Characteristics Of Sperical, Homogeneous, Two-Region, Molten-Fluoride-Salt-Reactors
Experimental Molten-Salt-Fueled 30MW Power Reactor
Molten-Salt Reactor Program Quarterly Progress Report: July 31, 1959
Corrosion Associated With Fluorination In The Oak Ridge National Laboratory Fluoride Volatility Process
Molten-Salt Reactor Program Quarterly Progress Report: Oct 31, 1959
Phase Equilibria In Molten Salt Breeder Reactor Fuels
Molten-Salt Reactor Program Quarterly Progress Report: Jan 31 And April 30, 1960
The Feasibility Of An Unattended Nuclear Power Plant
Molten-Salt Reactor Program Quarterly Progress Report: July 31, 1960
Molten-Salt Reactor Program Quarterly Progress Report: Feb 28, 1960
Molten-Salt Reactor Program Quarterly Progress Report: Aug 31, 1961
Molten-Salt Reactor Program Quarterly Progress Report: Feb 28, 1962
Thermodynamic Properties Of Molten-Salt Solutions
Recovery Of PuF6 By Fluorination Of Fused Fluoride Salts
Molten-Salt Reactor Program Quarterly Progress Report: Aug 31, 1962
Thermal Analysis And Gradient Quenching Apparatus And Techniques For tHe Investigation Of Fused Salt Phase Equilibria
Mixtures Of Metals With Molten Salts
Molten-Salt Reactor Program Quarterly Progress Report: Jan 31, 1963
Molten-Salt Reactor Program Quarterly Progress Report: July 31, 1963
Reduction Of Uranium Hexafluoride Retention On Beds Of Magnesium Fluoride Used For Removal Of Technetium Hexafluoride
Molten-Salt Reactor Program Quarterly Progress Report: Jan 31, 1964
Molten-Salt Reactor Program Quarterly Progress Report: July 31, 1964
Preliminary Design Study Of A Continuous Fluorination Vacuum Distillation System For Regenerating Fuel And Fertile Streams In A Molten Salt Breeder Reactor
Molten-Salt Reactor Program Quarterly Progress Report: Feb 28, 1965
Molten-Salt Reactor Program Quarterly Progress Report: Aug 31, 1965
Reactor Chemistry Division Annual Progress Report: Dec 31, 1965
Molten-Salt Reactor Program Quarterly Progress Report: Feb 28, 1966
Design Studies Of 1000MW(e) Molten-Salt Breeder Reactors
Molten-Salt Reactor Program Quarterly Progress Report: Aug 31, 1966
Development Of A Model For Computing 135Xe Migration In The MSRE
Reactor Chemistry Division Annual Progress Report: Dec 31, 1966
Molten-Salt Reactor Program Quarterly Progress Report: Feb 28, 1967
MSRE Control Elements: Manufacture, Inspection, Drawings, Ad Specifications
Gas Transportation In MSRE Moderator Graphite. I. Review Of Theory And Counterdiffusion Experiments
Molten-Salt Reactor Program Quarterly Progress Report: Aug 31, 1967
Fluorination Of Falling Droplets Of Molten Fluoride Salt As A Means Of Recovering Uranium And Plutonium
Zero-Power Physics Experiments On The Molten-Salt Reactor Experiment
Molten-Salt Reactor Program Quarterly Progress Report: Feb 28, 1968
An EMF Study Of LiF-BeF2 Solutions
Molten-Salt Reactor Program Quarterly Progress Report: Aug 31, 1968
Preperation Of Enriching Salt 7LiF-233UF4 For Refueling The Molten Salt Reactor
Gs Transport In MSRE Moderator Graphite
Molten-Salt Reactor Program Semiannual Progress Report: Feb 28, 1969
Liquid-Vapor Equilibria In LiF-BeF2 And Lif-BeF2-ThF4 Systems
Low-Pressure Distillation Of Molten Fluoride Mixtures: Nonradioactive Tests For The MSRE Distillation Experiment
Molten-Salt Reactor Program Semiannual Progress Report: Aug 31, 1969
Two Fluid Molten-Salt Breeder Reactor Design Study
Conceptual Design study Of A Single-Fluid Molten-Salt Breeder Reactor
Molten-Salt Reactor Program Quarterly Progress Report: Feb 28, 1970
Molten-Salt Fluoride Volatility Pilot Plant: recovery Of Enriched Uranium From Aluminum-Clad Fuel Elements
Corrosion In Polythermial Loop Systems
Low-Pressure Distillation Of A Portion Of The Fuel carrier Salts From The Molten Salt Reactor Experiment
preperation And Handling Of Salt Mixtures For The Molten Salt reactor Experiment
Molten-Salt Reactor Program Semiannual Progress Report: Aug 31, 1970
Chemical Aspects Of MSRE Operations
Molten-Salt Reactor Program Semiannual Progress Report: Feb 31, 1971
Molten-Salt Reactor Program Semiannual Progress Report: Aug 31, 1971
Molten-Salt Reactor Program Semiannual Progress Report: Feb 28, 1972
Molten-Salt Reactor Program Semiannual Progress Report: Aug 31, 1972
Intergranular Cracking Of INOR-8 In The MSRE
development Of The Variable-Gap Technique For Measuring The Thermal Conductivity Of Fluoride Salt Mixtures
Molten-Salt Reactor Program Quarterly Progress Report: Aug 31, 1972
Fission Product Behavior In The Molten Salt Reactor Experiment
Development And Construction Of A Molybdenum Test Stand
An Assessment Of Industrial energy Optics Based On Caol And Nuclear Systems
Molten-Salt Reactor Program Semiannual Progress Report: Aug 31, 1974
Program Plan For Development Of Molten-Salt Breeder Reactors
Molten-Salt Reactor Program Semiannual Progress Report: Feb 28, 1975
Molten-Salt Reactor Program Semiannual Progress Report: Aug 31, 1975
Molten-Salt Reactor Program Semiannual Progress Report: Feb 28, 1976
Engineering Tests Of The Metal transfer Process For Extraction Of Rare-earth Fission Products From A Molten-Salt Breeder Reactor Fuel Salt
Interim Assessment Of The Denatured 233U Fuel Cycle: Feasibility And Nonproliferation Characteristics
Uses for Uranium-233: What Should Be Kept For Future Needs?
Removal Of Tritium From The Molten Salt Breeder Fuel
Thermal-Stress And Strain-fatigue Analyses Of The MSRE Fuel And Coolent Pump Tanks
Water Test Development Of The Fuel Pump For The MSRE
Development Of Freeze Valve For Use In The MSRE
Effect Of Alloying Additions On Corrosion Behavior Of Nickel - Molybdenum Alloys In Fused Fluoride Mixtures
Murgatrotd - An IBM 7090 Program For The Analysis Of The Kinetics Of The MSRE
Safety Calculations For MSRE
576MW(t) Natural Convedtion Molten Salt Reactor Study
Corrosion Behavior Of Reactor Materials In Fluoride Salt Mixtures
Temperatures In The MSRE Core During Steady-State Power Operation
Temperature And Reactivity Coefficient Averaging In The MSRE
Prediction Of Effective Yields Of Delayed Neutrons In MSRE
Some Chemical Aspects Of Molten-Salt Reactor Safety
Analysis Of Filling Accidents In MSRE
Radiation Chemistry Of MSRE System
Design Studies And Cost Estimates Of Two Fluoride Volatility Plants
Design And Operation Of Forced-Circulation Corresion Testing Loops With Molten Salt
InHarent Neutron Sources In Clean MSRE Fuel Salt
MSRE Design And Operations Report Part 1: description Of Reactor Design
MSRE Design And Operations Report Part 2A: Nuclear And Process Instramentation
MSRE Design And Operations Report Part 2B: Nuclear And Process Instramentation
MSRE Design And Operations Report Part 3: Nuclear Analysis
MSRE Design And Operations Report Part 5: Reactor Safety Analysis Report
MSRE Design And Operations Report Part 6: Operating Safety Limits For The Molten-Salt Experiment
MSRE Design And Operations Report Part 6: Operating Safety Limits For The Molten-Salt Experiment
MSRE Design And Operations Report Part 7: Fuel Handeling And Processing Plant
MSRE Design And Operations Report Part 7: Fuel Handling And Processing Plant
MSRE Design And Operations Report Part 9: Safety Procedures And Emergency Plans
MSRE Design And Operations Report Part 10: Maintenance Equipment And Procedures
MSRE Design And Operations Report Part 11: Test Program
MSRE Neutron Source Requirements
Tensile And Creep Properties Of INOR-8 For The Molten-Salt reactor Experiment
Tube Pliugging In The Molten-Salt Reactor Experiment Primary Heat Exchanger
Reconstitution Of MSRE Fuel By Reducing UF6 Gas To UF4 In A Molten Salt
Mo;ten Salt Conversion Reactor - Design Study And Power Cost Estimates For A 1000MW(e) Station
Stability Analysis Of The Molten-Salt Ractor Eperiment
Oxide Chemistry And Thermodynamics Of Molten Lithium Fluoride- Beryllium Fluoride By Equilibration With Gaseous Water-Hydrogen Fluoride Mixtures
A Study Of Lead And Lead-Salt Corrosion In Thermal-Convection Loops
Simulators For Training Molten-Salt Reactyor Operators
Summary Of Molten-Salt Breeder Reactor Design Sudies
Removal Of Protactinium From Molten Fluoride Breeder Blanket Mixtures
Design Study Of A Heat-Exange System For One MSRE Concept
tests Of Various Particle Filters For removal Of Oil Mists And Hydrogen Vapor
Experimental Dynamic Analysis Of The Molten-Salt Reactor Experiment
Period Measurements On The Molten Salt Reactor Experiment During Fuel Circulation: Theory and Experiment
Considerations Of Low Pressure Distillation And Its Application To Processing Of Molten-Salt Breeder Ractor Fuels
The Reactivity Balance In The MSRE
A Model For Computing The Migration Of Very Short Lived Nobel gases Into MSRE Graphite
Summary Of The Objectives, The design, And A Program Of Development Of Molten-Salt Breeder Reactors
Fuel Blanket Processing Developemnt For Molten Salt Breeder Reactors
Chemical Research And Development For Molten Salt Breeder Reactors
MNaterials Development For Molten-Salt Breeder Reactors
Components And Systems For Molten-Salt Breeder Reactors
Instramentation And Controls Development For HC3.00 MN 65 Molten-Salt Breeder Reactors
Physics Program For Molten-Salt Breeder Reactors
Safety Program For Molten-Salt Breeder Reactors
Maintence Development For Molten-Salt Breeder Reactors
Review Of Molten-Salt Reactor Physics Calculations
Operation Of MoltenSalt Convection Loops In The ORR
A Literature Survey Of The Fluorides And OxyFluorides Of Molybdenum
Experience With High-Temperature Centrifugal Pumps In Nuclear Reactors And Their application To Molten-Salt Thermal Breeder Reactors
An Evaluation Of The Molten Salt reactor Eperiment Hastelloy N Surveillance Specimens - First Group
Assessment Of Candidate Molten Salt Coolants For The Advanced High-Temperature Reactor
Refueling Options And Considerations For Liquid-Salt-Cooled Very High Temperature Reactors
Assessment Of Nuclear-Hydrogen Synergies With Renewable Energy Systems And Coal Liquefaction Processes
An Account Of Oak Ridge National Laboratory's Thirteen Nuclear Reactors
Pre-Conceptual Design Of A Fluoride-Salt-Cooled SmallModular Advanced High-Temperature Reactor
Investigation Of One Concept Of A THermal Shield For The Room Housing A Molten-Salt Breeder Reactor
Closed Circuit Television Viewing In Maintenance Of Radioactive Systems At ORNL
Reduction Of Iron Dissolved In Molten LiF-ThF4
Measurement Of The Relative Volatilities Of Fluorides Of Ce, La, Nd, Sm, Eu, Ba, Sr, T And Zr In Mixtures Of LiF And BeF2
Tube Vibration In MSRE Primary Heat Exchanger
MSRE Design And Operations Report Part V-A: Safety Analysis Of Operation With 233U
Graphite Behavior And Its Effects On MSBR Performance
Electrical Conductivity Of Molar Fluorides
Design Of An engineering-Scale, Vacuum Distillation Experiment For Molten-Salt Reactor Fuel
Photon Reactoion Analysis For Lithium And Fluoride In Graphite Using A Slit Scanning Technique
Removal Of xenon-135 From Circulating Fuel Salt Of The MSBR By Mass Transfer To Helium Bubbles
Chemical FeasibilityOf Fueling Molten Salt Reactors With PuF3
Irradiation Behavior Of Cladding And Structural Materials
Preliminary Study Of A Molten-Salt Burst Reactor
MSRE Design And Operations Report Part 11A: Test Program For U233 Operation
Postirradiation Tensile And Creep-Rupture Of Several Experimantal Heats And Incoloy 800 At 770 And 760DegC
Measurement Of Helium Void Fraction In The MSRE
Physical Properties Of Molten-Salt Reactor Fuel, Coolant, And Flush Salts
Determination Of The Void Fraction In The MSRE Using Small Induced Pressure Perturbations
Solubility Of Cerium Trifluoride In Molten Salt Mixtures Of LiF, BeF2 And ThF4
An Evaluation Of The Molten-Salt Reactor Experiment Hastelloy N Surveillance Specimans - Second Group
Bubbles, Drops And Entrainment In Molten Salts
Dynamic Analysis Of A Salt Supercritical Water Heat Exchanger And Throttle Used With MSBR
Design, Construction And Testing Of A Large Molten Salt Filter
Some Aspects Of The Thermodynamics Of The Extraction Of Uranium, Thorium And Rare Earths From Molten LiF-BeF2 Into Liquid Li-Bi Solutions
MSBR Control Studies
Compatibility Of Hastelloy N And Oroly 9M With NaBF4-NaF-KBF4 (90-4-4 Mole %) Fluoborate Salt
Theoretical Dynamic Analysis Of The MSRE With 233U Fuel
Processing Of The MSRE Flush And Fuel Salts
Fractional Crystallization Reactions In The System LiF-BeF2-ThF4
Conceptual Sstem Design Description Of The Salt Pump Test Stand For THe Molten Salt Breeder Experiment
An Evaluation Of The Molten-Salt Reactor Experiment Hastelloy N Surveillance Specimans - Third Group
Management Of NobleGas Fission Product Waste From Reprocessing Spent Fuels
InHerent Neutron Source In MSRE With Clean 233U Fuel
Feasibility Study Of Remote Cutting And Selding For Nuclear Plant Maintenance
Compatibility Of molybdenum-Base Alloy TZM With LiF-BeF2-ThF4-UF4 (68-20-11.7-0.3 mole %) At 1100 DegC
Catastrophic Corrosion Of Type 304 Stainless Steel In A System Circulating Fused Sodium Fluoroborate
Core Irradiation-Specimen Array For MSRE Runs 19 And 20
Preliminary Systems Design Description (Title 1 Design) Of The Salt Pump Test Stand For The Molten Salt Breeder Experiment
Computer Programs For The MSRE Heat Exchangers
Tensile Properties Of Hastelloy N Welded After Irradiation
Control Studies Of A 1000MW(e) MSBR
Parametric Survay Of The Effects Of Major Parameters On The Design Of Fuel-To-Inert-Salt Heat Exchangers For The MSBR
A NEw Approach To The design Of Steam Generators For Molten Salt Reactor Power Plants
Calculated Radioactivity Of MSRE Fuel Salt
Plans For Post-Operation Examination Of The NMolten-Salt Reactor Experiment
Compatibility Of Fused Sodium Fluoroborates By BF3 Gas With Hastelloy N Alloys
Development Of Fuel And Coolent Centrifugal Pumps For The Molten-Salt Reactor Experiment
Experimental Dynamic Analysis Of The MSBR With 233U Fuel
Quality Assurance Procedures In Construction And Maintenance Of The Molten-Salt reactor Experiment
Reactor Power Measurement And Heat Transfer Performance In The Molten Salt Reactor Experment
An Extended Hydraulic Model Of The MSRE Circulating Fuel System
Spray, Mist, Bubbles, And Foam In The Molten Salt Reactor Experment
MSRE Systenms And Components Performance
MSRE Operator Training And Operating Techniques
Engineering Development Studies For Molten-Salt Breeder Reactor Processing No 1
An Evaluation Of The Molten-Salt Reactor Experiment Hastelloy N Surveillance Specimans - Fourth Group
Influence Of Titanium, Zirconium And Hafnium Additions On The resistance Of Modified Hastelloy N To Irradiation Damage at High Temperature - Phase 1
MSBR Control Studies: Analog Simulation Program
Engineering Development Studies For Molten-Salt Breeder Reactor Processing No 2
Engineering Development Studies For Molten-Salt Breeder Reactor Processing No 3
Engineering Development Studies For Molten-Salt Breeder Reactor Processing No 4
Engineering Development Studies For Molten-Salt Breeder Reactor Processing No 5
Engineering Development Studies For Molten-Salt Breeder Reactor Processing No 6
Fluorine Production And Recombination In Frozen MSR Salts fter Reactor Operation
Thermal Radiation Transfer Of Afterheat In MSBR Exchangers
A Study Of Fission Products In The Molten_Salt Reactor experiment By Gamma Spectrometery
Molten Salt Breeder Experiment Design Bases
Fluid Dynamic Studies Of The Molten-Salt reactor experiment (MSRE) Core
MSRE Procedures For The Period Between Examination And Ultimate Disposal
Engineering Development Studies For Molten-Salt Breeder Reactor Processing No 7
Engineering Development Studies For Molten-Salt Breeder Reactor Processing No 8
Further Discussion Of Instramentation And Controls Development Needed For The Molten Salt Breeder
Thermal Stability Of Titanium-Modified Hastelloy N At 650 And 760 DegC
Experience With Sodium Fluoroborate In An MSRE-Scale Facility
Engineering Development Studies For Molten-Salt Breeder Reactor Processing No 10
Rod: A Nuclear And Fuel-Cycle Analysis Code For Circulating-Fuel Reactors
Estimated Cost Of Adding A Third Salt-Circulating System For Controlling Tritium Migration In The 1000MW(e) MSBR
Xenon Behavior In The Molten Salt Reactor Experiment
Mass Transfer Between Hastelloy N And Haynes Alloy No 25 In A Molten Sodium Fluoroborate Mixture
Operstion Of The Sampler-Enricher In The Molten Salt Reactor Experiment
Solution Of The Equation describing The Interface Between Two Fluids For The Volume Pressure Attached, Sessile Shaped, bubbles And Drops
Remote Inspection Of Welded Joints
Availability Of Natural resources For Molten-Salt Breeder Reactors
Design And cost Study Of A Fluorination - reductive extraction - Metal transfer Processing Plant For The MSBR
A Study Of The adherence Of Tungsten And Molybdenum Coatings
Mass transfer Between mall Bubbles And Liquids In Cocurrent Turbulent Pipeline Flow
Estimatd Behavior Of Titanium In MSBR Chemical Processing Systems
Hybrid Computer Simulation Of The MSBR
Heat Transfer Salt For High Temperature Steam Generation
Design Studies Of A Molten-Salt Reactor Demonstration Plant
Design And Operation Of A Forced-Circulation Corrosion Test Facitily (MSR_FCL-1) employing Hastelloy N Alloy And Sodium Fluoroborate Salt
Corrosion And Mass transfer Characteristics Of NaBF4-NaF (92 - 8 Mole%) In Hastelloy N
The Migration Of A Class Of Fission Products (Noble Metals) In The Molten-Salt reactor Experiment
MSR Component replacements using remote Cutting And Welding Techniques
Zero-Power experiments With 233U in The MSRE
Molten Salts As Blanket Fluids In Controlled Fusion Reactors
The Equilibrium Of Dilute UF3 Solutions Contained In Graphite
Forced-Convection Heat Transfer Measurements With A Molten Fluoride Salt Mixture Flowing In A Smooth Tube
Development Of A Venturi Type Bubble Generator For Use In The Molten-Salt Reactor Xexon Removal System
Corrosion Of Type 304LStainless Steel And Hastelloy N By Mixtures Of Boron Trifluoride, Air And Argon
Postirradiation examination Of Materials From The MSRE
Improved Repersentation Of Some Aspects Of Circulating-Fuel Reactor Kinetics
Effect Of FeF2 Addition On Mass Transfer In A Hastelloy N - LiF-BeF2-UF4 Thermal Convection Loop System
Evaluation Of Hastelloy N Alloys After Nine Years exposure To Both A Molten Fluoride Salt And Air At Temperatures From 700 To 560 DegC
MRPP - Mulitregional Processing Plant Code
A Forced Circulation Loop For Corrodsion Studies: Hastelloy N Compatibility with NaBF4 - NaF (92 - 8 Mole %)
Mass Transfer Between Hasteloy N And A Molten Sodium Fluoroborate Mixture In A Thermal Convection Loop
Compatatibility Of Brazing Alloys And The Molten Salt NaBF4 - 8 Mole Percent NaF At 610 DegC
Alloy Compatibility With LiF-BeF2 Salts Containg ThF4 And UF4
Engineering Development Studies For Molten-Salt Breeder Reactor Processing No 18
The Molten-Salt Reactor information System
A Method For Calculating The Steady-State distribution Of Tritium In A Molten-Salt Breeder Reactor Plant
Engineering Development Studies For Molten-Salt Breeder Reactor Processing No 19
Engineering Development Studies For Molten-Salt Breeder Reactor Processing No 20
Engineering Development Studies For Molten-Salt Breeder Reactor Processing No 21
A Study Of Tritium Removal From fusion reactor Blankets Of Molten Salt And Lithium-Aluminum
Conceptual design Of A Continouos Fluorinator experimantal Facility (CFEF)
Efvaluation Of Alternate Secondary (And Tertiary) Coolents For The Molten-Salt Breeder Reactor
Heat Transfer Measurements In A Forced Convection Loop With Two Molten-Fluoride Salts: LiF-BeF2-Thf$-Uf$ And Eutectic NaBF4-NaF
Temperature Gradient Compatibility Tests Of Some refractory Metals And alloys In Bismuth And bismuth-Lithium Solutions
System Design Description Of Forced-Convection Molten-Salt Corrosion Loops MSR-FCL-3 And MSR-FCL-4
Survey Of Technology For Storage Of Thermal Energy In Heat Transfer Salt
Distribution And Behavior Of tritium In The Coolant-Salt technology Facility
Corrosion Of Several Metals In Supercriticxal Steam At 583 DegC
The Corrosion resistance Of Type 316 stainless Steel To Li2BeF4
Compatibility Studies Of Potential Molten-Salt Breeder Reactor Materials In Molten Fluoride Salts
Status Of Materials Development For Molten Salt Reactors
Status Of Tellurium hastelloy N Studies In Molten Fluoride Salts
Molten salt Reactors For efficient Nuclear Fuel Utilization Without Plutonium Seperation
Development Status And Potential Program For Development Of proliferation-resistant Molten-Salt Reactors
Enviromental Assessment Of Alternate FBR Fuels: Radiological Assessment Of Airborne releases From Thorium Mining And Milling
Conceptual Design characteristics Of A Denatured Molten-Salt reactor with Once-Through Fueling
Thermal Convection Loop Studies Of The Corrosion oF Fe-Ni-Cr Alloys By Molten NaNO3-KNO3
extended Storage-In-Place Of MSRE Fuel Salt And Flush Salt
Nuclear Power Options Viability Study Vol 1: Executive Summary
Nuclear Power Options Viability Study Vol 2: Reactor Concepts, Descriptions And Assessments
Nuclear Power Options Viability Study Vol 3: Nuclear Discipline Topics
Nuclear Power Options Viability Study Vol 4: Bibliography
Reaction Of Utranium Oxides With Chlorine And Carbon Or Carbon Monoxide To Prepare Uranium Chlorides
Literature Information Applicable To The reaction Of Uranium Oxides With Chlorine To Prepare Uranium Tetrachloride
Materials Considerations For Molten Salt Accelerator Based Plutonium Conversion Systems
A Descriptive Model Of The Molten Salt Reactor Experiment After Shutdown: review Of FY 1995 Progress
Isotopic Dilution Requirements For 233U Critically Safety In Processing And Disposal Facilities
Strategy For The Future Use And Disposition Of Uranium-233: Technical Information
Disposition Options For Uranium-233
Practical Aspects Of Liquid Salt Cooled Fast Neutron Reactors
Capital Cost Evaluation 1000MW(e) Molten Salt converter Reactor Power Plants
Table Of Isometric Masses And Natural Abundances
New Boiling Salt Fast Breeder Reactor Concepts
Thermochemical Production Of Hydrogen From Solar And Nuclear Energy
Perspectives Of The Thorium Fuel Cycle
Potential Of Thorium Molten salt Reactors: Detailed Calculations And Concept Evolutions In View Of A Large Nuclear Energy Production
Report Of The Fluid Fuel Reactors Task Force To The Division Of Reactor Development
1000MW(e) Molten Salt Breeder Reactor Conceptual Design Study
Molten Salt Critical Reactors For The Transmutation Of Transuranics And Fission Products
The Use Of Thorium in Nuclear Power Reactors
Cost Benefit Analysis Of The US Nuclear Program
Updated (1970) Cost Benefit Analysis Of The US Breeder Reactor Program
An Evaluation Of The Molten Salt Breeder Reactor
Indexed Abstracts Of Selected References On Molten-Salt Reactor Technology
defination Of Weapon Usable Uranium-233