Quarterly technical report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, April--June 1975

Technical Report · Sat Nov 01 04:00:00 EST 1975

DOI:https://doi.org/10.2172/4061298· OSTI ID:4061298

The current water reactor safety activities of ANC are accomplished in four programs. The Semiscale Program consists of small-scale nonnuclear thermal- hydraulic experiments for the generation of experimental data that can be applied to analytical models describing loss-of-coolant accident (LOCA) phenomena in water-cooled nuclear power plants. Emphasis is placed on acquiring system effects data from integral tests that characterize the most significant thermal- hydraulic phenomena during the depressurization (blowdown) and emergency cooling phase of a LOCA. The LOFT Program provides test data to support: (a) assessment and improvement of the analytical methods utilized for predicting the behavior of pressurized water reactors (PWR) under LOCA conditions; (b) evaluation of the performance of PWR engineered safety features (ESF), particularly the emergency core cooling system (ECCS); and (c) assessment of the quantitative margins of safety inherent in the performance of these safety features. The Thermal Fuels Behavior Program is a program designed to provide information on the behavior of reactor fuels under normal, off-normal, and accident conditions. The experimental portion is concentrated on testing of single fuel rods and fuel rod clusters under power-cooling-mismatch (PCM), loss-of-coolant, and reactivity initiated accident conditions. The Reactor Behavior Program encompasses the analytical aspects of predicting the response of nuclear power reactors under normal, abnormal, and accident conditions. The status of each program is reported. (auth)

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: E(10-1)-1375
• NSA Number: NSA-33-022304
• OSTI ID: 4061298
• Report Number(s): ANCR--1262
• Country of Publication: United States
• Language: English

Related Subjects

*BWR TYPE REACTORS-- REACTOR SAFETY
*LOFT REACTOR-- PLANNING
*PWR TYPE REACTORS-- REACTOR SAFETY
*REACTOR SAFETY-- RESEARCH PROGRAMS
220900* --Nuclear Reactor Technology--Reactor Safety
BLOWDOWN
COMPUTER CODES
ECCS
ENGINEERED SAFETY SYSTEMS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MOCKUP
N77100 --Reactors--Power Reactors
Non-breeding
Light-water Moderated
Boiling Water-cooled
N77200 --Reactors--Power Reactors
Non-breeding
Light-water Moderated
Non-boiling Water-cooled
N77900* --Reactors--Reactor Safety & Environmental Aspects