Published February 2004 | Version v1
Miscellaneous Metadata-only

Actinide isotopes compositions and neutrons emission rate calculations for irradiated research reactors fuel

Creators

  • 1. Reactors Dept., Nuclear Research Center, Atomic Energy Authority, Cairo (Egypt)

Description

the availability of burn-up data is an essential first step in any systematic approach to the enhancement of safety, economics and performance of research reactors. A computer program has been designed to solve the system of equations describing the depletion, decay and production of uranium, plutonium and transplutonium nuclides. monte Carlo code was used to calculate the effective one group microscopic cross sections averaged over ETRR-1 fuel cell. the compositions of actinide isotopes, burn-up and neutrons emission rate have been calculated as a function of irradiation time and cooling time. results indicate that the amount of plutonium produced and neutrons emission rate are strongly dependent on the fuel burn-up

Availability note (English)

Available from the Egyptian Society of Nuclear Sciences and Applications
Part of:
Proceedings of the Eighth Conference of Nuclear Sciences and Applications

Additional details

Publishing Information

Imprint Title
Proceedings of the Eighth Conference of Nuclear Sciences and Applications, Vol.II
Imprint Pagination
750 p.
Journal Page Range
p. 436-447
Report number
INIS-EG--178(I.II)

Conference

Title
8. International Conference of Nuclear Sciences and Applications
Dates
7-12 Feb 2004
Place
Cairo (Egypt)

INIS

Country of Publication
Egypt
Country of Input or Organization
Egypt
INIS RN
36016048
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ACTINIDES; BURNUP; CALCULATION METHODS; COMPUTER CODES; CROSS SECTIONS; DECAY; ECONOMICS; ETRR-1 REACTOR; ISOTOPE RATIO; MONTE CARLO METHOD; PLUTONIUM; SAFETY; SPENT FUELS; TRANSPLUTONIUM COMPOUNDS; URANIUM
Descriptors DEC
ACTINIDES; CALCULATION METHODS; ELEMENTS; ENERGY SOURCES; FUELS; MATERIALS; METALS; NUCLEAR FUELS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TRANSURANIUM COMPOUNDS; TRANSURANIUM ELEMENTS

Optional Information