Physics of reactor safety. Quarterly report, January--March 1977. [LMFBR]

Technical Report · Wed Jun 01 00:00:00 EDT 1977

DOI:https://doi.org/10.2172/5442947· OSTI ID:5442947

This report summarizes work done on reactor safety, Monte Carlo analysis of safety-related critical assembly experiments, and planning of DEMI safety-related critical experiments. Work on reactor core thermal-hydraulics is also included.

• Research Organization: Argonne National Lab., Ill. (USA)
• Sponsoring Organization: US Energy Research and Development Administration (ERDA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 5442947
• Report Number(s): ANL-77-48
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
REACTOR SAFETY
RESEARCH PROGRAMS
CLINCH RIVER BREEDER REACTOR
CONTROL ELEMENTS
CONTROL ROD WORTHS
FLUID FLOW
HEAT TRANSFER
LOSS OF FLOW
MATHEMATICAL MODELS
PRIMARY COOLANT CIRCUITS
REACTIVITY COEFFICIENTS
REACTIVITY INSERTIONS
REACTIVITY WORTHS
REACTOR ACCIDENTS
VOID COEFFICIENT
ACCIDENTS
BREEDER REACTORS
COOLING SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
POWER REACTORS
REACTIVITY
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
SODIUM COOLED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding