Validation of the code package MCPV

The results of the validation of the code package MCPV that is used in the radiation exposure determination methodology for the pressure vessels of the VVER type reactors of Ukrainian NPPs are presented. The validation is carried out on the basis of the data obtained with the reactor LR-0 benchmark...

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Main Authors: V. N. Bukanov, O. V. Grytsenko, V. L. Diemokhin, O. M. Pugach, S. M. Pugach
Format: Article
Language:English
Published: Institute for Nuclear Research, National Academy of Sciences of Ukraine 2009-06-01
Series:Âderna Fìzika ta Energetika
Subjects:
Online Access:http://jnpae.kinr.kiev.ua/10.2/Articles_PDF/jnpae-2009-10-0165-Bukanov.pdf
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author V. N. Bukanov
O. V. Grytsenko
V. L. Diemokhin
O. M. Pugach
S. M. Pugach
author_facet V. N. Bukanov
O. V. Grytsenko
V. L. Diemokhin
O. M. Pugach
S. M. Pugach
author_sort V. N. Bukanov
collection DOAJ
description The results of the validation of the code package MCPV that is used in the radiation exposure determination methodology for the pressure vessels of the VVER type reactors of Ukrainian NPPs are presented. The validation is carried out on the basis of the data obtained with the reactor LR-0 benchmark and of the results of dosimetry measurements behind reactor pressure vessels. It is shown the code package MCPV can be used to simulate the neutron transport through a complicated heterogeneous environment of nuclear reactor and to obtain the calculational values of functionals of the neutron flux influencing onto its pressure vessel.
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spelling doaj.art-a62402e7f46b43c38b497d5e1edb7b382022-12-21T19:17:42ZengInstitute for Nuclear Research, National Academy of Sciences of UkraineÂderna Fìzika ta Energetika1818-331X2074-05652009-06-01102165170Validation of the code package MCPVV. N. Bukanov0O. V. Grytsenko1V. L. Diemokhin2O. M. Pugach3S. M. Pugach4Institute for Nuclear Research, National Academy of Sciences of Ukraine, Kyiv, UkraineInstitute for Nuclear Research, National Academy of Sciences of Ukraine, Kyiv, UkraineInstitute for Nuclear Research, National Academy of Sciences of Ukraine, Kyiv, UkraineInstitute for Nuclear Research, National Academy of Sciences of Ukraine, Kyiv, UkraineInstitute for Nuclear Research, National Academy of Sciences of Ukraine, Kyiv, UkraineThe results of the validation of the code package MCPV that is used in the radiation exposure determination methodology for the pressure vessels of the VVER type reactors of Ukrainian NPPs are presented. The validation is carried out on the basis of the data obtained with the reactor LR-0 benchmark and of the results of dosimetry measurements behind reactor pressure vessels. It is shown the code package MCPV can be used to simulate the neutron transport through a complicated heterogeneous environment of nuclear reactor and to obtain the calculational values of functionals of the neutron flux influencing onto its pressure vessel.http://jnpae.kinr.kiev.ua/10.2/Articles_PDF/jnpae-2009-10-0165-Bukanov.pdfreactor pressure vesselradiation exposureneutron transport codevalidation.
spellingShingle V. N. Bukanov
O. V. Grytsenko
V. L. Diemokhin
O. M. Pugach
S. M. Pugach
Validation of the code package MCPV
Âderna Fìzika ta Energetika
reactor pressure vessel
radiation exposure
neutron transport code
validation.
title Validation of the code package MCPV
title_full Validation of the code package MCPV
title_fullStr Validation of the code package MCPV
title_full_unstemmed Validation of the code package MCPV
title_short Validation of the code package MCPV
title_sort validation of the code package mcpv
topic reactor pressure vessel
radiation exposure
neutron transport code
validation.
url http://jnpae.kinr.kiev.ua/10.2/Articles_PDF/jnpae-2009-10-0165-Bukanov.pdf
work_keys_str_mv AT vnbukanov validationofthecodepackagemcpv
AT ovgrytsenko validationofthecodepackagemcpv
AT vldiemokhin validationofthecodepackagemcpv
AT ompugach validationofthecodepackagemcpv
AT smpugach validationofthecodepackagemcpv