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Dosimetry for Decommissioning of Nuclear Power Plants

Rachamin, R.; Konheiser, J.; Barkleit, A.; Seidl, M.

In this study, a 3D detailed Monte-Carlo (MC) model of a German PWR was developed to calculate the neutron fluence characteristics within the ex-vessel components of the reactor. The neutron fluence prediction capability of the developed model was validated based on metal foil-activation measurements. Metal foil-activation measurement has been successfully used in reactor dosimetry for many years. It is an ideal method for collecting information on neutron fluence in an active reactor. This paper gives an overview of the MC model of the reactor and presents the foils activation measurement procedure. Then, the results of the MC simulations and the experimental measurements are presented and discussed.

Keywords: German PWR; Decommissioning; Neutron fluence; Activation; MCNP; Validation

  • Contribution to proceedings
    14th International Conference on Radiation Shielding and 21st Topical Meeting of the Radiation Protection and Shielding Division (ICRS 14/RPSD 2022), 25.-29.09.2022, Seattle, USA
  • Lecture (Conference)
    14th International Conference on Radiation Shielding and 21st Topical Meeting of the Radiation Protection and Shielding Division (ICRS 14/RPSD 2022), 25.-29.09.2022, Seattle, USA

Permalink: https://www.hzdr.de/publications/Publ-35541
Publ.-Id: 35541