Published 1977
| Version v1
Book
Prediction of the CRBRP outlet plenum transient response following a reactor trip
Creators
Description
An assessment was made of the ability of a numerical hydro computer code, VARR-II, to accurately predict the transient response of the outlet plenum of the Clinch River Breeder Reactor Plant, following a reactor trip. Analytical model size and representation of the internals, located in the outlet plenum, were varied and a model to represent the outlet plenum was selected. Using this analytical model, the calculated temperature response compared favorably with experimental data, which included the effects of flow stratification following a simulated reactor trip
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York
- Imprint Pagination
- 8 p.
Conference
- Title
- National heat transfer conference.
- Dates
- 15 - 17 Aug 1977.
- Place
- Atlantic City, New Jersey, United States of America (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8347197
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLINCH RIVER BREEDER REACTOR; HYDRODYNAMICS; REACTOR COMPONENTS; SPATIAL DISTRIBUTION; TRANSIENTS
- Descriptors DEC
- BREEDER REACTORS; DISTRIBUTION; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID MECHANICS; LIQUID METAL COOLED REACTORS; MECHANICS; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS
Optional Information
- Secondary number(s)
- CONF-770802--5.