Published 1999
| Version v1
Miscellaneous
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Source Term Determination in MPR Reactor Core
Creators
- 1. National Center for Nuclear Safety and Radiation Control Atomic Energy Authority, Cairo (Egypt)
Description
The source term is determined for MPR reactor at normal operation conditions for fuel irradiated one year at full power in an equilibrium core. Calculations were carried out using the code ORIGEN-IR and results obtained for different time intervals after shutdown were: Decay heat (thermal power) in Watt and the peak heat flux in the core, Radioactivity in Curies for the light, heavy, and fission product elements, Isotopes inventory Results were compared with those given in the safety analysis report of the reactor
Files
31026708.pdf
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(180.4 kB)
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the international conference on hazardous waste sources, effects and management
- Imprint Pagination
- 1555 p.
- Journal Page Range
- p. 327-332
- Report number
- INIS-EG--165(v.1,2,3)
Conference
- Title
- International conference on hazardous waste sources, effects and management
- Dates
- 12-16 Dec 1998
- Place
- Cairo (Egypt)
INIS
- Country of Publication
- Egypt
- Country of Input or Organization
- Egypt
- INIS RN
- 31026708
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT; FISSION PRODUCTS; FUEL ELEMENTS; HEAT FLUX; IRRADIATION; RADIOACTIVITY; SOURCE TERMS; WATT FISSION SPECTRUM
- Descriptors DEC
- ISOTOPES; MATERIALS; NEUTRON SPECTRA; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; SPECTRA