Analysis of the influence of nuclear fuel burnup on the 16N formation rate in the primary coolant of the WWER-1000 reactor

The developed model of the WWER-1000 reactor using MCNP6.2 (Monte Carlo N-Particle Transport Code) includes the detailed core taking into account the design of the fuel assemblies, as well as the baffle, the lower plenum, the fuel support columns, the core barrel, a downcomer, and the reactor pressu...

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Main Authors: Yu. Fylonych, V. Zaporozhan, O. Balashevskyi, K. Merkotan
Format: Article
Language:English
Published: Institute for Nuclear Research, National Academy of Sciences of Ukraine 2021-03-01
Series:Âderna Fìzika ta Energetika
Subjects:
Online Access:http://jnpae.kinr.kiev.ua/22.1/Articles_PDF/jnpae-2021-22-0048-Fylonych.pdf
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spelling doaj-a9ffdab4bc184aefacea8682c20eca662021-06-29T15:15:52ZengInstitute for Nuclear Research, National Academy of Sciences of UkraineÂderna Fìzika ta Energetika1818-331X2074-05652021-03-012214855https://doi.org/10.15407/jnpae2021.01.048Analysis of the influence of nuclear fuel burnup on the 16N formation rate in the primary coolant of the WWER-1000 reactorYu. Fylonych0V. Zaporozhan1O. Balashevskyi2K. Merkotan3Department of the Scientific and Technical Support, Odesa SS "Scientific and Technical Support" of SE NNEGC "Energoatom", Odesa, UkraineDepartment of the Scientific and Technical Support, Odesa SS "Scientific and Technical Support" of SE NNEGC "Energoatom", Odesa, UkraineDepartment of the Scientific and Technical Support, Odesa SS "Scientific and Technical Support" of SE NNEGC "Energoatom", Odesa, UkraineDepartment of the Scientific and Technical Support, Odesa SS "Scientific and Technical Support" of SE NNEGC "Energoatom", Odesa, UkraineThe developed model of the WWER-1000 reactor using MCNP6.2 (Monte Carlo N-Particle Transport Code) includes the detailed core taking into account the design of the fuel assemblies, as well as the baffle, the lower plenum, the fuel support columns, the core barrel, a downcomer, and the reactor pressure vessel. It allows implementing multifunctional calculations such as recriticality with various fuel configurations, the critical concentration of boric acid, determination of the axial and radial peaking factor in the reactor core, etc. For obtaining the more precise result of the cumulation nitrogen-16 formation rate, the contribution from different water volumes was taken into account: in the core, above the fuel and the top nozzle, in the top nozzle of the fuel assembly, in the bottom nozzle, between the fuel and the bottom nozzle, in the axial channels of the baffle, in the reflector. In order to obtain the realistic boundary conditions, the change of the isotopic composition in the fuel assemblies during one fuel cycle was calculated using the ORIGEN-ARP of SCALE software. Therefore, the influence of the nuclear fuel depletion of fuel assemblies in the WWER-1000 reactor on the change of the basic neutron-physical characteristics was determined such as the distribution of the neutron flux density with the energies necessary to initiate the 16O(n,p)16N reaction, the average number of neutrons per fission, the neutron spectrum and average fission energy. As a result, the dependence of the nitrogen-16 formation rate in the primary coolant system on the nuclear fuel burnup is obtained.http://jnpae.kinr.kiev.ua/22.1/Articles_PDF/jnpae-2021-22-0048-Fylonych.pdfwwer-1000coolant activationnitrogen-16mcnp codereaction rateorigen-arpburnup
collection DOAJ
language English
format Article
sources DOAJ
author Yu. Fylonych
V. Zaporozhan
O. Balashevskyi
K. Merkotan
spellingShingle Yu. Fylonych
V. Zaporozhan
O. Balashevskyi
K. Merkotan
Analysis of the influence of nuclear fuel burnup on the 16N formation rate in the primary coolant of the WWER-1000 reactor
Âderna Fìzika ta Energetika
wwer-1000
coolant activation
nitrogen-16
mcnp code
reaction rate
origen-arp
burnup
author_facet Yu. Fylonych
V. Zaporozhan
O. Balashevskyi
K. Merkotan
author_sort Yu. Fylonych
title Analysis of the influence of nuclear fuel burnup on the 16N formation rate in the primary coolant of the WWER-1000 reactor
title_short Analysis of the influence of nuclear fuel burnup on the 16N formation rate in the primary coolant of the WWER-1000 reactor
title_full Analysis of the influence of nuclear fuel burnup on the 16N formation rate in the primary coolant of the WWER-1000 reactor
title_fullStr Analysis of the influence of nuclear fuel burnup on the 16N formation rate in the primary coolant of the WWER-1000 reactor
title_full_unstemmed Analysis of the influence of nuclear fuel burnup on the 16N formation rate in the primary coolant of the WWER-1000 reactor
title_sort analysis of the influence of nuclear fuel burnup on the 16n formation rate in the primary coolant of the wwer-1000 reactor
publisher Institute for Nuclear Research, National Academy of Sciences of Ukraine
series Âderna Fìzika ta Energetika
issn 1818-331X
2074-0565
publishDate 2021-03-01
description The developed model of the WWER-1000 reactor using MCNP6.2 (Monte Carlo N-Particle Transport Code) includes the detailed core taking into account the design of the fuel assemblies, as well as the baffle, the lower plenum, the fuel support columns, the core barrel, a downcomer, and the reactor pressure vessel. It allows implementing multifunctional calculations such as recriticality with various fuel configurations, the critical concentration of boric acid, determination of the axial and radial peaking factor in the reactor core, etc. For obtaining the more precise result of the cumulation nitrogen-16 formation rate, the contribution from different water volumes was taken into account: in the core, above the fuel and the top nozzle, in the top nozzle of the fuel assembly, in the bottom nozzle, between the fuel and the bottom nozzle, in the axial channels of the baffle, in the reflector. In order to obtain the realistic boundary conditions, the change of the isotopic composition in the fuel assemblies during one fuel cycle was calculated using the ORIGEN-ARP of SCALE software. Therefore, the influence of the nuclear fuel depletion of fuel assemblies in the WWER-1000 reactor on the change of the basic neutron-physical characteristics was determined such as the distribution of the neutron flux density with the energies necessary to initiate the 16O(n,p)16N reaction, the average number of neutrons per fission, the neutron spectrum and average fission energy. As a result, the dependence of the nitrogen-16 formation rate in the primary coolant system on the nuclear fuel burnup is obtained.
topic wwer-1000
coolant activation
nitrogen-16
mcnp code
reaction rate
origen-arp
burnup
url http://jnpae.kinr.kiev.ua/22.1/Articles_PDF/jnpae-2021-22-0048-Fylonych.pdf
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AT obalashevskyi analysisoftheinfluenceofnuclearfuelburnuponthe16nformationrateintheprimarycoolantofthewwer1000reactor
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