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AbstractAbstract
[en] The Battelle Revised Thermos code, that solves the integral neutron transport equation is used to perform the analysis of a chosen system, which includes materials and number densities that are typically encountered in gaseous core reactors, where selected parameters as pressure (or number density, if the gas temperature is kept constant) of the hydrogen; and temperature and material of the external moderator are changed. (author)
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Source
Associacao Brasileira de Energia Nuclear, Rio de Janeiro, RJ (Brazil); [800 p.]; 2000; p. 370-373; 12. Brazilian national meeting on reactor physics and thermal hydraulics; 12. Encontro nacional de fisica de reatores e termo-hidraulica; Rio de Janeiro, RJ (Brazil); 15-20 Oct 2000; 8. General congress on nuclear energy; 8. Congresso geral de energia nuclear; Rio de Janeiro, RJ (Brazil); 15-20 Oct 2000; 5. Brazilian national meeting on nuclear applications; 5. Encontro nacional de aplicacoes nucleares; Rio de Janeiro, RJ (Brazil); 15-20 Oct 2000; 2 refs., 5 tabs.
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Multimedia
Literature Type
Conference; Numerical Data
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