ISSN: 1546-962X
CODEN: JAIOAD
Page Count: 7

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

Borodkin, G
Head of Reactor Dosimetry Group (Borodkin), Head of Department (Khrennikov), Scientific and Engineering Centre for Nuclear and Radiation Safety (SEC NRS) of Rostechnadozor, Moscow,

Khrennikov, N
Head of Reactor Dosimetry Group (Borodkin), Head of Department (Khrennikov), Scientific and Engineering Centre for Nuclear and Radiation Safety (SEC NRS) of Rostechnadozor, Moscow,

Böhmer, B
Guest ScientistForschungszentrum Rossendorf e.V. (FZR), Dresden,

Noack, K
Head of Department (Noack), Research Scientist (Konheiser), Forschungszentrum Rossendorf e.V. (FZR), Dresden,

Konheiser, J
Head of Department (Noack), Research Scientist (Konheiser), Forschungszentrum Rossendorf e.V. (FZR), Dresden,

(Received 20 June 2005; accepted 29 September 2005)

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.

Keywords:
VVER, neutron-gamma transport calculation, ex-vessel activation measurements

Paper ID: JAI13460
DOI: 10.1520/JAI13460
ASTM International is a member of CrossRef.