Physics of Reactor Safety (Quarterly Report, July - September 1976)

Technical Report · Tue Nov 30 23:00:00 EST 1976

DOI:https://doi.org/10.2172/7110983· OSTI ID:7110983

Reports are presented on reactor safety research and technical coordination of the RSR safety analysis program by members of the Reactor Safety Appraisals Group, Monte Carlo analysis of safety-related critical assembly experiments by members of the Theoretical Fast Reactor Physics Group, and planning of DEMO safety-related critical experiments by members of the Zero Power Reactor (ZPR) Planning and Experiments Group. Work on reactor core thermal-hydraulic performed in the Components Technology Division is also included.

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Energy Research and Development Administration (ERDA); USNRC
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 7110983
• Report Number(s): ANL-77-9
• Country of Publication: United States
• Language: English

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ACCIDENTS
BREEDER REACTORS
COMPUTER CODES
CRBR
EPITHERMAL REACTORS
EXCURSIONS
FAST REACTORS
FBR TYPE REACTORS
Fast Reactor
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MELTDOWN
MONTE CARLO METHOD
Monte Carlo
Nuclear Criticality Safety Program (NCSP)
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
Reactivity
SAFETY
SIMULATION
Safety Analysis
Safety Research
TEMPERATURE GRADIENTS