Article ID Journal Published Year Pages File Type
1729086 Annals of Nuclear Energy 2012 10 Pages PDF
Abstract

The neutron fluence load on a reactor pressure vessel is an important physical quantity affecting material degradation and consequently reliable assessment of pressure vessel integrity and lifetime prolongation beyond designed conditions. This degradation is influenced by mixed neutron–photon source from the core periphery as well as by material parameters of the reactor pressure vessel. Computational procedures and experimental determination of neutron fluxes in the VVER-1000 mock-up internal structures as well as the results achieved are described in this paper. The calculation were performed with the MCNPX code with different nuclear data libraries. Nuclear data were processed using NJOY code.The neutron spectra measurements were performed with a two-parameter stilbene spectrometer.

► Measurement of neutron fluxes behind reactor pressure vessel of VVER-1000 mock-up. ► Calculations of neutron fluxes behind reactor pressure vessel using various data libraries. ► Discrepancies between calculation and experiment of neutron fluxes behind reactor pressure vessel.

Related Topics
Physical Sciences and Engineering Energy Energy Engineering and Power Technology
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