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Deterministic and Monte Carlo Neutron Transport Calculation for Greifswald-1 and Comparison with Ex-vessel Measured Data Pages: 7 Published: Jan 2007
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View License Agreement Source: STP1490-EB 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 crosssectional groups on the calculation results is demonstrated. Keywords: VVER, neutron-gamma transport calculation, ex-vessel activation measurements Paper ID: STP45450S Committee/Subcommittee: E10.07 DOI: 10.1520/STP45450S ASTM International is a member of CrossRef. | ||