Water Reactor Safety Research Division. Quarterly progress report, January 1--March 31, 1979

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

OSTI ID:6107496

Romano, A J ^[1]

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1. comp.

The Water Reactor Safety Research Programs Quarterly Report describes current activities and technical progress in the programs sponsored by the USNRC Division of Reactor Safety Research. The projects reported each quarter are the following: LWR Thermal Hydraulic Development, RAMONA Code Evaluation, TRAC Code Assessment, and Stress Corrosion Cracking of PWR Steam Generator Tubing.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: EY-76-C-02-0016
• OSTI ID: 6107496
• Report Number(s): NUREG/CR-0821; BNL-NUREG-51015
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
REACTOR SAFETY
RESEARCH PROGRAMS
WATER COOLED REACTORS
INCONEL 600
STRESS CORROSION
PWR TYPE REACTORS
STEAM GENERATORS
ALLOYS
BOILERS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
COMPUTER CODES
CORROSION
ENERGY TRANSFER
FLUID FLOW
INCONEL ALLOYS
IRON ALLOYS
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIOBIUM ALLOYS
REACTORS
SAFETY
VAPOR GENERATORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled