Published 1987
| Version v1
Book
Real time boiling water reactor core simulation
Description
The authors discuss the Westinghouse real time boiling water reactor core model has been derived from the BWR nuclear design code POLCA. In particular, the cross section treatment is identical to that currently used in POLCA. Using design code methodology assures that reactor core response is accurately predicted over the entire range of conditions from cold shutdown to hot full power without reliance on empirical adjustments. This first principles approach to simulation allows the model to directly calculate difficult phenomena such as the reverse power effect
Additional details
Publishing Information
- Publisher
- Society for Computer Simulation.
- Imprint Place
- San Diego, CA (USA)
- ISBN
- 0-911801-20-0
- Imprint Title
- Proceedings of the 1987 summer computer simulation conference
- Imprint Pagination
- 1021 p.
- Journal Page Range
- p. 403-406.
Conference
- Title
- 19. annual summer computer simulation conference.
- Dates
- 27-30 Jul 1987.
- Place
- Montreal (Canada).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21028694
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; FUEL RODS; P CODES; REACTOR CORES; REACTOR SHUTDOWN; REACTOR SIMULATORS; RELIABILITY; SPECIFICATIONS; WESTINGHOUSE STANDARD REACTOR
- Descriptors DEC
- ANALOG SYSTEMS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUNCTIONAL MODELS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SHUTDOWN; SIMULATORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-870706--.