Verification of void effect calculation
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:411779
- Institute of Nuclear Sciences Vinca, Belgrade (Yugoslavia)
The void effect is one of the most important phenomena linked to safety criteria. The presence of a coolant void and high absorption in a reactor core restricts validity of the diffusion approximation in calculations. The classic method used for averaging neutron cross sections in these cases does not offer a satisfactory solution, while transport and Monte Carlo methods are not acceptable in routine applications. New techniques based on space-energy core homogenization, such as the SPH method or the discontinuity factor method, are proposed instead.
- OSTI ID:
- 411779
- Report Number(s):
- CONF-951006--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 73; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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