Water Reactor Safety Research Division. Quarterly progress report, April 1-June 30, 1980
The Water Reactor Safety Research Programs quarterly report describes current activities and technical progress in the programs at Brookhaven National Laboratory sponsored by the USNRC Division of Reactor Safety Research. The projects reported each quarter are the following: LWR Thermal Hydraulic Development, Advanced Code Evlauation, TRAC Code Assessment, and Stress Corrosion Cracking of PWR Steam Generator Tubing.
- Research Organization:
- Brookhaven National Lab. (BNL), Upton, NY (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5277743
- Report Number(s):
- NUREG/CR-1618; BNL-NUREG-51255; ON: TI850159085
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
REACTOR SAFETY
RESEARCH PROGRAMS
WATER COOLED REACTORS
COMPUTER CODES
INCONEL 600
LOSS OF COOLANT
PWR TYPE REACTORS
STEAM GENERATORS
T CODES
TUBES
ACCIDENTS
ALLOYS
BOILERS
CHROMIUM ALLOYS
INCONEL ALLOYS
IRON ALLOYS
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIOBIUM ALLOYS
REACTOR ACCIDENTS
REACTORS
SAFETY
VAPOR GENERATORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
REACTOR SAFETY
RESEARCH PROGRAMS
WATER COOLED REACTORS
COMPUTER CODES
INCONEL 600
LOSS OF COOLANT
PWR TYPE REACTORS
STEAM GENERATORS
T CODES
TUBES
ACCIDENTS
ALLOYS
BOILERS
CHROMIUM ALLOYS
INCONEL ALLOYS
IRON ALLOYS
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIOBIUM ALLOYS
REACTOR ACCIDENTS
REACTORS
SAFETY
VAPOR GENERATORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety