Physics of Reactor Safety (Quarterly Report, April - June 1976)
Reports 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 are presented.
- 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:
- 7232569
- Report Number(s):
- ANL-76-114
- Country of Publication:
- United States
- Language:
- English
Similar Records
Physics of reactor safety. Quarterly report, April--June 1975
Physics of Reactor Safety (Quarterly report, January - March 1976)
Physics of Reactor Safety (Quarterly Report, July - September 1976)
Technical Report
·
Tue Dec 31 23:00:00 EST 1974
·
OSTI ID:4081190
Physics of Reactor Safety (Quarterly report, January - March 1976)
Technical Report
·
Sun Aug 01 00:00:00 EDT 1976
·
OSTI ID:7176976
Physics of Reactor Safety (Quarterly Report, July - September 1976)
Technical Report
·
Tue Nov 30 23:00:00 EST 1976
·
OSTI ID:7110983
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
Accident Analysis
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
COMPUTER CODES
CRBR
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
Fast Reactor
KINETICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MELTDOWN
MONTE CARLO METHOD
Nuclear Criticality Safety Program (NCSP)
POWER REACTORS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR KINETICS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
Reactivity Coefficients
SAFETY
SODIUM COOLED REACTORS
Worth Distribution
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
Accident Analysis
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
COMPUTER CODES
CRBR
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
Fast Reactor
KINETICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MELTDOWN
MONTE CARLO METHOD
Nuclear Criticality Safety Program (NCSP)
POWER REACTORS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR KINETICS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
Reactivity Coefficients
SAFETY
SODIUM COOLED REACTORS
Worth Distribution