The influence of core power distribution on neutron flux density behind a pressure vessel of a VVER-1000 Mock Up in LR-0 reactor

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F18%3AN0000030" target="_blank" >RIV/26722445:_____/18:N0000030 - isvavai.cz</a>

Alternative codes found

RIV/60162694:G43__/18:00536190 RIV/00216224:14330/18:00103752

Result on the web

<a href="http://dx.doi.org/10.1016/j.apradiso.2018.09.005" target="_blank" >http://dx.doi.org/10.1016/j.apradiso.2018.09.005</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.apradiso.2018.09.005" target="_blank" >10.1016/j.apradiso.2018.09.005</a>

Result language

angličtina

Original language name

The influence of core power distribution on neutron flux density behind a pressure vessel of a VVER-1000 Mock Up in LR-0 reactor

Original language description

The neutron flux distribution behind a reactor pressure vessel (RPV) is an important parameter that is monitored to determine neutron fluence in the RPV. Together with mechanical testing of surveillance specimens, these are the most important parts of in-service inspection programs that are essential for a realistic and reliable assessment of the RPV residual lifetime. The fast neutron fluence values are determined by a calculation. These calculation results are accompanied by measurements of induced activities of the activation foils placed in the capsules behind the RPV at selected locations, namely in azimuthal profile. In case of discrepancies between the measured and calculated activities of the activation foils placed behind the pressure vessel, it is difficult to determine the source of the deviation. During such analysis, there arises a question on the influence of power peaking near core boundary on neutron profile behind the RPV. This paper compares the calculated and measured increase of the neutron flux density distribution behind the reactor pressure vessel in the azimuthal profile that has arisen from the replacement of 164 fuel pins located close to reactor internals by pins with the higher enrichment. This work can be understood as the first step in the characterization of the effect of incorrectly calculated pin power or burn-up in the fuel assembly at the core boundary relative to the neutron flux distribution behind reactor pressure vessel. Based on a good agreement between the calculated and experimental values, it can be concluded that the mathematical model used to evaluate the power increase is correct.

Czech name

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Czech description

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Type

J_imp - Article in a specialist periodical, which is included in the Web of Science database

CEP classification

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OECD FORD branch

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Project

Result was created during the realization of more than one project. More information in the Projects tab.

Continuities

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Publication year

2018

Confidentiality

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Name of the periodical

Applied Radiation and Isotopes

ISSN

0969-8043

e-ISSN

—

Volume of the periodical

142

Issue of the periodical within the volume

December

Country of publishing house

GB - UNITED KINGDOM

Number of pages

10

Pages from-to

12-21

UT code for WoS article

000454462500003

EID of the result in the Scopus database

2-s2.0-85053761767