Applicability of LR-0 mock-up results to VVER-1000 reactor pressure vessel issues
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F16%3AN0000001" target="_blank" >RIV/26722445:_____/16:N0000001 - isvavai.cz</a>
Result on the web
<a href="http://dx.doi.org/10.1016/j.anucene.2016.07.027" target="_blank" >http://dx.doi.org/10.1016/j.anucene.2016.07.027</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.anucene.2016.07.027" target="_blank" >10.1016/j.anucene.2016.07.027</a>
Alternative languages
Result language
angličtina
Original language name
Applicability of LR-0 mock-up results to VVER-1000 reactor pressure vessel issues
Original language description
Evaluation of neutron fluence in a reactor pressure vessel (RPV) together with surveillance specimen programs for RPV materials are one of the most important parts of in-service inspection programs that are necessary for realistic and reliable assessment of RPV residual lifetime. This paper covers transport of neutrons through the RPV of a VVER-1000 nuclear reactor. This problem is of increased importance as it concerns issues around VVER NPP life extension. With regards to the construction (reduced thickness of the lateral reflector), this issue plays greater role in VVER reactors than in Western types of PWR reactors. RPV material degradation depends mainly on neutron flux and spectra. Both quantities can be calculated or measured. This paper compares MCNP calculations and measurements on zero-power experimental reactor LR-0 with TORT calculations for VVER-1000. The goal is to find a reasonable method for precise estimation of neutron fluence and attenuation factor through the RPV. The calculations were performed with MCNP stochastic code and TORT deterministic transport code. The measurements were performed in a VVER-1000 mock-up placed in reactor LR-0 (Research Center Rez).
Czech name
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Czech description
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Classification
Type
J<sub>x</sub> - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)
CEP classification
JF - Nuclear energy
OECD FORD branch
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Result continuities
Project
<a href="/en/project/ED2.1.00%2F03.0108" target="_blank" >ED2.1.00/03.0108: Sustainable Energy</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2016
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Annals of Nuclear Energy
ISSN
0306-4549
e-ISSN
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Volume of the periodical
98
Issue of the periodical within the volume
December
Country of publishing house
GB - UNITED KINGDOM
Number of pages
9
Pages from-to
157-165
UT code for WoS article
000383820400015
EID of the result in the Scopus database
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