Published 1983
| Version v1
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Study of an hypothetical reactor meltdown accident for a 50 MW sub(th) fast reactor
Description
A melhodology for determining the energy released in hypothetical reactor meltdown accidents is presented. A numerical code was developed based upon the Nicholson method for a uniform and homogeneous reactor with spherical geometry. A comparative study with other know programs in the literature which use better approximations for small energy released, shows that the methodology used were compatible with those under comparison. Besides the influence of some parameters on the energy released, such as the initial power level and the prompt neutron lifetime was studied under this metodology and its result exhibitted. The Doppler effect was also analyzed and its influence on the energy released has been emphasized. (Author)
Availability note (English)
MF available from INIS under the Report Number.Abstract (Portuguese)
Estuda-se uma metodologia para se estimar a energia liberada no nucleo de um reator rapido de potencia, em que esteja ocorrendo um acidente em que o nucleo do reator esteja se fundindo, este acidente e classificado como maximo. Desenvolveu-se um programa em Fortran com base no modelo de Nicholson, para um reator com geometria esferica, uniforme e homogenea. Fez-se um estudo comparativo com outro modelo desenvolvido, que utiliza melhores aproximacoes para baixas energias liberadas, e os resultados mostraram ser bastante coerentes. Estudou-se tambem a influencia na energia liberada de varios parametros, tais como potencia inicial, tempo de vida dos neutrons prontos e outros. O efeito Doppler tambem foi analisado e notou-se que possui grande influencia na analise de um acidente classificado como maximo, podendo limitar a energia liberada para niveis bem baixos. (Autor)Files
15056822.pdf
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Additional details
Additional titles
- Original title (Portuguese)
- Estudo de um acidente classificado como maximo em um reator rapido de 50 MW sub(th)
Publishing Information
- Imprint Pagination
- 97 p.
- Report number
- INIS-BR--136
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 15056822
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; DOPPLER EFFECT; E CODES; FAST REACTORS; MAXIMUM CREDIBLE ACCIDENT; SIMULATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; DESIGN BASIS ACCIDENTS; EPITHERMAL REACTORS; REACTOR ACCIDENTS; REACTORS