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Calculation of Neutron Fluence and Energy Release in WWER-1000 Structural Components Using Monte Carlo Method

Authors :
A. Abdullaiev
S. Soldatov
S. Chernitskyi
V. Hann
Source :
Nuclear and Radiation Safety. :11-17
Publication Year :
2018
Publisher :
State Scientific and Technical Center for Nuclear and Radiation Safety, 2018.

Abstract

The paper describes the methodology for the calculation of neutron fluence and energy release in WWER-1000 reactor cavity and baffle using the Monte Carlo MCNPX code. It formulates an approach to the simulation of a 3-D neutron source and conditions for the transport of neutrons and photons in the core. The research presents preliminary results of neutron fluence and energy release calculation in WWER-1000 reactor cavity and baffle.

Details

ISSN :
20736231
Database :
OpenAIRE
Journal :
Nuclear and Radiation Safety
Accession number :
edsair.doi...........8870915eb88055219babd02e2e63dcb1
Full Text :
https://doi.org/10.32918/nrs.2018.1(77).02