Predicting Ex-core Detector Response in a PWR with Monte Carlo Neutron Transport Methods

Autor: Goričanec Tanja, Kotnik Domen, Štancar Žiga, Snoj Luka, Kromar Marjan
Jazyk: angličtina
Rok vydání: 2020
Předmět:
Zdroj: EPJ Web of Conferences, Vol 225, p 03007 (2020)
Druh dokumentu: article
ISSN: 2100-014X
DOI: 10.1051/epjconf/202022503007
Popis: An approach for calculating ex-core detector response using Monte Carlo code MCNP was developed. As a first step towards ex-core detector response prediction a detailed MCNP model of the reactor core was made. A script called McCord was developed as a link between deterministic program package CORD-2 and Monte Carlo code MCNP. It automatically generates an MCNP input from the CORD-2 data. A detailed MCNP core model was used to calculate 3D power distributions inside the core. Calculated power distributions were verified by comparison to the CORD-2 calculations, which is currently used for core design calculation verification of the Krško nuclea power plant. For the hot zero power configuration, the deviations are within 3 % for majority of fuel assemblies and slightly higher for fuel assemblies located at the core periphery. The computational model was further verified by comparing the calculated control rod worth to the CORD-2 results. The deviations were within 50 pcm and considered acceptable. The research will in future be supplemented with the in-core and ex-core detector signal calculations and neutron transport outside the reactor core.
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