Published 1984
| Version v1
Miscellaneous
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Dynamic power behavior of a PWR type nuclear reactor
Description
A methodology for the power level evaluation (dynamic behavior) in a Pressurized Water Reactor, during a transient is developed, by solving the point kinetic equation related to the control rod insertion effects and fuel or moderator temperature 'feed-back'. A new version of the thermal-hydraulic code COBRA III P/MIT, is used. In this new version was included, as an option, the methodology developed. (E.G.)
Availability note (English)
MF available from INIS under the Report Number.Abstract (Portuguese)
Desenvolve-se uma metodologia para a avaliacao do nivel de potencia (comportamento dinamico) de um reator nuclear, PWR, durante um transiente, atraves da solucao das equacoes de cinetica pontual, associadas aos efeitos da insercao de barras de controle e de realimentacao de temperatura do moderador e do combustivel. Usa-se a nova versao do programa de analise termo-hidraulica-COBRA/III P/MIT. Nesta nova versao foi incorporada, de forma opcional, a metodologia desenvolvida, necessaria para o conhecimento do comportamento do nucleo do reator. (E.G.)Files
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Additional details
Additional titles
- Original title (Portuguese)
- Comportamento dinamico da potencia do reator nuclear tipo PWR
Publishing Information
- Imprint Pagination
- 163 p.
- Report number
- INIS-BR--289
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 16058410
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- C CODES; COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; POWER DISTRIBUTION; PWR TYPE REACTORS; REACTOR KINETICS EQUATIONS; TEMPERATURE DEPENDENCE; TRANSIENTS
- Descriptors DEC
- COMPUTER CODES; DISTRIBUTION; ENRICHED URANIUM REACTORS; EQUATIONS; POWER REACTORS; REACTORS; SIMULATION; SPATIAL DISTRIBUTION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS