Journal Published Online: 01 January 2006
Volume 3, Issue 4

Deterministic and Monte Carlo Neutron Transport Calculation for Greifswald-1 and Comparison with Ex-vessel Measured Data

CODEN: JAIOAD

Abstract

The results of a study of neutron and gamma field functionals derived by deterministic Sn and Monte Carlo calculation methods and by neutron activation measurements in application to the ex-vessel cavity of the VVER-440 reactor Greifswald-1 are presented. A good agreement of deterministic and stochastic calculation results with each other as well as with measurement results was found for neutron threshold detector reaction rates at ex-vessel positions. The influence of different numbers of cross-sectional groups on the calculation results is demonstrated.

Author Information

Borodkin, G
Scientific and Engineering Centre for Nuclear and Radiation Safety (SEC NRS) of Rostechnadozor, Moscow, Russia
Khrennikov, N
Scientific and Engineering Centre for Nuclear and Radiation Safety (SEC NRS) of Rostechnadozor, Moscow, Russia
Böhmer, B
Forschungszentrum Rossendorf e.V. (FZR), Dresden, Germany
Noack, K
Forschungszentrum Rossendorf e.V. (FZR), Dresden, Germany
Konheiser, J
Forschungszentrum Rossendorf e.V. (FZR), Dresden, Germany
Pages: 7
Price: $25.00
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Details
Stock #: JAI13460
ISSN: 1546-962X
DOI: 10.1520/JAI13460