Reactor Development Program (Progress Report, June 1962)

Technical Report · Sun Jul 15 04:00:00 EDT 1962

DOI:https://doi.org/10.2172/4811413· OSTI ID:4811413

Adams, R. M. ^[1]

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1. Argonne National Lab. (ANL), Argonne, IL (United States)

Research and development progress is reported on water-cooled reactors, liquid metal-cooled reactors, general reactor technology, plutonium recycle, advance systems research and development, and nuclear safety. Topics covered include the EBWR, BORAX-V, EBR-I, EBR-II, FARET, applied reactor physics, reactor fuels development, reactor materials development, reactor components development, heat engineering and fluid flow, chemical separations, Argonne Advanced Research Reactor, subcritical reactor as substitute for isotope sources, thermal reactor safety studies, fast reactor safety studies, and direct conversion studies.

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
• DOE Contract Number: W-31109-ENG-38
• NSA Number: NSA-16-028358
• OSTI ID: 4811413
• Report Number(s): ANL-6580
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
42 ENGINEERING
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BORAX-5
BORAX-V
CHEMICAL REACTIONS
CONVERSION
CP-6
CRITICALITY
EBR- 1
EBR-2
EBWR
FARET
FAST NEUTRONS
FLUID FLOW
FUELS
HEAT TRANSFER
HEATING
LIQUID METAL COOLANT
MACHINE PARTS
Nuclear Criticality Safety Program (NCSP)
Nuclear Safety
PLANNING
PLUTONIUM
REACTOR SAFETY
REACTORS
REPROCESSING
RESEARCH REACTORS
Reactor Safety
SEPARATION PROCESSES
THERMAL NEUTRONS
THERMIONICS
WATER COOLANT
Water-Cooled Reactor