Published September 1993
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Calculation of neutron flux in the presence of a source
Description
Neutron sources are introduced into the reactors to initiate the chain reaction. For safety reasons, we have to know the distribution and evolution of the flux throughout the startup phase. The flux is calculated iteratively but convergence of the process can slow down arbitrarily as we approach criticality. A calculation method is presented, with a convergence speed which does not depend on the negative reactivity when it is small. (author). 7 refs
Availability note (English)
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Additional details
Additional titles
- Original title (French)
- Calcul du flux neutronique en presence d'une source
Publishing Information
- Imprint Pagination
- 9 p.
- Report number
- EDF--94-NJ-00094
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 26052971
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CALCULATION METHODS; NEUTRON FLUX; NEUTRON SOURCES; REACTOR START-UP
- Descriptors DEC
- PARTICLE SOURCES; RADIATION FLUX; RADIATION SOURCES; START-UP