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Reactor Dosimetry Issues During Justification of Extension of Service Life of Nonrestorable Equipment of Russian VVER

Borodkin, G.
Head of group (G. Borodkin), Head of Department (N. Khrennikov), and Deputy Director (A. Dmitriev),SEC NRS of Rostechnadzor,

Khrennikov, N.
Head of group (G. Borodkin), Head of Department (N. Khrennikov), and Deputy Director (A. Dmitriev),SEC NRS of Rostechnadzor,

Dmitriev, A.
Head of group (G. Borodkin), Head of Department (N. Khrennikov), and Deputy Director (A. Dmitriev),SEC NRS of Rostechnadzor,

Miroshnichenko, M.
Head of Department (M. Miroshnichenko) and Deputy Head of Department (V. Grivizirsky),Rostechnadzor,

Grivizirsky, V.
Head of Department (M. Miroshnichenko) and Deputy Head of Department (V. Grivizirsky),Rostechnadzor,

Pages: 8    Published: Jan 2007

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Source: STP1490-EB

Abstract

Reactor dosimetry issues have been analyzed in every aspect of extension of service life of non-restorable equipment of the Russian Vodo-Vodianoy Energetichesky Reactor (rus.) (VVER)-type reactors. A special attention has been focused on the role of neutron fluence and fluence rate uncertainties in prediction of the lifetime of the equipment. Results of analysis of service life justification of the first generation VVERs have been presented. A comparison of calculational and experimental dosimetry results are discussed in this paper. Usefulness of the Niobium-93 technique of fluence measurements as applied to template and trepan specimen dosimetry is especially emphasized in this paper.

Keywords:
reactor dosimetry, VVER, service life, pressure vessel, support structures, fluence, calculation

Paper ID: STP45421S
Committee/Subcommittee: E10.08
DOI: 10.1520/STP45421S
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