Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, April--June 1978

Technical Report · Sat Jul 01 04:00:00 EDT 1978

DOI:https://doi.org/10.2172/6891047· OSTI ID:6891047

Water reactor safety research is summarized for the following programs: Semiscale, LOFT, thermal fuels behavior, code development and analysis, code verification and applications, and the 3-D protect. The Semiscale Program reports the performance of the first two tests in the new Mod-3 system and an evaluation of two LOFT counterpart tests, one (Test S-06-3) an NRC standard problem. The LOFT Experimental Program reports significant results from the final test in the nonnuclear test series and summarizes the objectives of the first LOFT nuclear test series. The Thermal Fuels Behavior Program reports on the various test series in the PBF reactor (including results of a power-cooling-mismatch test), and presents discussions of failed fuel rod behavior and vapor explosion criteria. The Code Development and Analysis Program reports progress in developing an improved version of the RELAP4 code and a successful linking of two codes, RELAP4 (a blowdown reflood code) and FRAP-T (a fuel analysis code). The Code Verification and Applications Program reports progress in verifying the RELAP4/MOD6 and FRAP-T4 codes and describes the NRC/RSR Data Bank Program, which is intended to collect, store, and provide access to experiment data on reactor safety. The multinational 3-D Experiment Project reports design, analysis, and instrumentation development in support of German and Japanese reflood experiments.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 6891047
• Report Number(s): NUREG/CR-0252; TREE-1219
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360204 -- Ceramics
Cermets
& Refractories-- Physical Properties
ACCIDENTS
ACTINIDE COMPOUNDS
BLOWDOWN
BWR TYPE REACTORS
CHALCOGENIDES
COMPUTER CALCULATIONS
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FUEL ELEMENTS
FUEL-CLADDING INTERACTIONS
HEAT TRANSFER
LOFT REACTOR
LOSS OF COOLANT
MATHEMATICAL MODELS
OPERATION
OXIDES
OXYGEN COMPOUNDS
PBF REACTOR
PERFORMANCE
PHYSICAL PROPERTIES
PLUTONIUM COMPOUNDS
PLUTONIUM DIOXIDE
PLUTONIUM OXIDES
POWER-COOLING-MISMATCH ACCIDENTS
PRESSURE GRADIENTS
PULSED REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
SAFETY
SIMULATION
TANK TYPE REACTORS
TEST REACTORS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
TRANSURANIUM COMPOUNDS
TWO-PHASE FLOW
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS