Published 1986 | Version v1
Miscellaneous Metadata-only

Development of calculation method for one-dimensional kinetic analysis in fission reactors, including feedback effects

Creators

  • 1. Instituto Militar de Engenharia, Rio de Janeiro (Brazil). Secao de Engenharia Nuclear

Description

The calculation method used in WIGLE code is studied. Because of the non availability of such a praiseworthy solution, expounding the method minutely has been tried. This developed method has been applied for the solution of the one-dimensional, two-group, diffusion equations in slab, axial analysis, including non-boiling heat transfer, accountig for feedback. A steady-state program (CITER-1D), written in FORTRAN 4, has been implemented, providing excellent results, ratifying the developed work quality. (Author)

Abstract (Portuguese)

Estuda-se o metodo de calculo utilizado no codigo WIGLE. Devido a nao disponibilidade desta solucao, destrinchou-se tal metodo aplicado a solucao das equacoes unidimensionais de difusao de neutrons a dois grupos, em geometria plana, analise axial, considerando-se efeitos de realimentacao devidos a: temperatura, Xenonio e controle, com transferencia de calor em regime de nao ebulicao. Desenvolveu-se um program (CITER-1D), em FORTRAN4, para estudo estacionario. Os resultados obtidos estao de pleno acordo com os fornecidos por WIGL3. CITER-1D e computacionalmente rapido e extremamente versatil, devido a sua constituicao modular. O metodo destrinchado se constitui em importante ferramenta para solucao numerica de equacoes unidimensionais diferenciadas no tempo. (Autor)

Additional details

Additional titles

Original title (Portuguese)
Desenvolvimento de metodo de calculo para analise cinetica unidimensional, em reatores a fissao, compreendendo efeitos de realimentacao

Publishing Information

Imprint Title
Proceedings of the 1. General Congress of Nuclear Energy. v. 1
Imprint Pagination
430 p.
Journal Page Range
v. 1 p. 268-271.
Report number
INIS-BR--537(v.1)

Conference

Title
1. General Congress of Nuclear Energy.
Dates
17-20 Mar 1986.
Place
Rio de Janeiro, RJ (Brazil).

INIS

Country of Publication
Brazil
Country of Input or Organization
Brazil
INIS RN
17073186
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
C CODES; COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; HEAT TRANSFER; MATHEMATICAL MODELS; NEUTRON DIFFUSION EQUATION; NUCLEAR POWER PLANTS; NUMERICAL SOLUTION; ONE-DIMENSIONAL CALCULATIONS; SLABS; STEADY-STATE CONDITIONS; TEMPERATURE DEPENDENCE; TIME DEPENDENCE; W CODES; XENON
Descriptors DEC
COMPUTER CODES; ELEMENTS; ENERGY TRANSFER; NONMETALS; NUCLEAR FACILITIES; POWER PLANTS; RARE GASES; SIMULATION; THERMAL POWER PLANTS

Optional Information

Notes
Imprint:Anais do 1. Congresso Geral de Energia Nuclear. v. 1.