Reactor safety research programs. Quarterly report, January 1--March 31, 1979. [BWR; PWR]

Technical Report · Tue May 01 00:00:00 EDT 1979

DOI:https://doi.org/10.2172/6107495· OSTI ID:6107495

Hooper, J L ^[1]

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1. comp.

Progress is summarized in the following LWR safety-related studies: (1) ultimate heat sink performance; (2) verification of steady-state fuel performance computer codes; (3) acoustic emission-flow relationship for pressure vessel monitoring; (4) fuel subassembly procurement and irradiation; (5) steam generator tube integrity prediction; (6) core thermal model development; and (7) integration of nondestructive examination reliability and fracture mechanics. (HDR)

• Research Organization: Battelle Pacific Northwest Labs., Richland, WA (United States)
• DOE Contract Number: EY-76-C-06-1830
• OSTI ID: 6107495
• Report Number(s): NUREG/CR-0855; PNL-3040-1
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR SAFETY
PWR TYPE REACTORS
RESEARCH PROGRAMS
ACOUSTIC EMISSION TESTING
COOLING PONDS
ECCS
FAILURES
FUEL ASSEMBLIES
FUEL ELEMENTS
IN-SERVICE INSPECTION
MATHEMATICAL MODELS
PERFORMANCE
PRESSURE VESSELS
REACTOR CORES
STEAM GENERATORS
TUBES
ACOUSTIC TESTING
BOILERS
CONTAINERS
ENGINEERED SAFETY SYSTEMS
INSPECTION
MATERIALS TESTING
NONDESTRUCTIVE TESTING
PONDS
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
REACTORS
SAFETY
SURFACE WATERS
TESTING
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WATER RESERVOIRS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
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Light-Water Moderated
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