Deterministic and Monte Carlo neutron transport calculation for Greifswald-1 and comparison with ex-vessel measurement data

Deterministic and Monte Carlo neutron transport calculation for Greifswald-1 and comparison with ex-vessel measurement data

Borodkin, G.; Khrennikov, N.; Böhmer, B.; Noack, K.; Konheiser, J.

Neutron and gamma field functionals were studied by means of deterministic Sn and stochastic Monte Carlo calculations and by neutron activation measurements that were carried out in the ex-vessel cavity of the VVER-440 reactor Greifswald-1. The paper presents and analyses the results. The influence of different numbers of energy groups for the description of the cross sections is pointed out. A good agreement was found both between the results of deterministic and Monte Carlo calculation and between numerical and measurement results.

Keywords: VVER reactors; neutron-gamma transport calculations; Sn method; Monte Carlo method; ex-vessel reactor cavity; neutron activation measurements

  • Lecture (Conference)
    12 th International Symposium on Reactor Dosimetry, 08.-13.05.2005, Gatlinburg, United States
  • Journal of ASTM International 3(2006)4
  • Contribution to proceedings
    12 th International Symposium on Reactor Dosimetry, 08.-13.05.2005, Gatlinburg, United States
    Reactor Dosimetry: 12th International Symposium, West Conshohocken: ASTM, 978-0-8031-3412-6

Permalink: https://www.hzdr.de/publications/Publ-7490