Published 1976
| Version v1
Miscellaneous
Open
Contribution to the study of the evolution of nuclear fuel composition in PWR type reactors. Reactor cores in three and four regions of enrichment
Description
The main methods for calculations of fuel depletion are studied and some approaches to do it are mentioned; the LEOPARD Code is described and full details are given for each subroutine, flow charts are included; the method given by the code for calculation of fuel depletion is described; some imperfections from the IPR's version are listed, and corrected, for instance: the method for burn-up calculation of heavy isotopes; the results of calculations for a reference reactor based on data of the Preliminary Safety Analysis Report (PSAR) for Angra I Nuclear Plant are presented and discussed. (author)
Availability note (English)
MF available from INIS under the Report Number.Abstract (Portuguese)
Estudam-se os principais metodos de calculo da evolucao do combustivel e mencionam-se aproximacoes para efetua-los; descreve-se o codigo LEOPARD, detalhando cada sub-rotina e incluindo fluxogramas; descreve-se o processo usado pelo codigo para os calculos de evolucao do combustivel; enumeram-se falhas da versao disponivel no IPR e fazem-se modificacoes, entre as quais, o modo de se calcular a queima dos isotopos pesados; apresentam-se e discutem-se os calculos para um reator de referencia, baseado em dados do relatorio Preliminar de Analise de Seguranca da Central de Angra I (RPAS). (autor)Files
21007813.pdf
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Additional details
Additional titles
- Original title (Portuguese)
- Contribuicao ao estudo da evolucao da composicao do combustivel em reatores tipo PWR. Nucleos a tres e a quatro regioes de enriquecimento
Publishing Information
- Imprint Pagination
- 170 p.
- Report number
- INIS-BR--1696
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 21007813
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- ANGRA-1 REACTOR; BURNUP; L CODES; NUCLEAR FUELS; SPENT FUELS
- Descriptors DEC
- COMPUTER CODES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; POWER REACTORS; PWR TYPE REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS