SYMPOSIA PAPER Published: 01 January 2007
STP45450S

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

Source

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 crosssectional groups on the calculation results is demonstrated.

Author Information

Borodkin, G.
Scientific and Engineering Centre for Nuclear and Radiation Safety (SEC NRS) of Rostechnadzor, Moscow, Russia
Khrennikov, N.
Scientific and Engineering Centre for Nuclear and Radiation Safety (SEC NRS) of Rostechnadzor, 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
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Details
Developed by Committee: E10
Pages: 245–251
DOI: 10.1520/STP45450S
ISBN-EB: 978-0-8031-6242-6
ISBN-13: 978-0-8031-3412-6