KOŠŤÁL, M., V. RYPAR, E. LOSA, D. HARUT, M. SCHULC, V. KLUPÁK, Zdeněk MATĚJ, František CVACHOVEC, B. JÁNSKÝ, E. NOVÁK, T. CZAKOJ, V. JUŘÍČEK and S. ZARITSKY. The influence of core power distribution on neutron flux density behind a pressure vessel of a VVER-1000 Mock Up in LR-0 reactor. Applied Radiation and Isotopes. Elsevier, 2018, vol. 142, Dec, p. 12-21. ISSN 0969-8043. Available from: https://dx.doi.org/10.1016/j.apradiso.2018.09.005.
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Basic information
Original 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
Authors KOŠŤÁL, M. (203 Czech Republic), V. RYPAR (203 Czech Republic), E. LOSA (203 Czech Republic), D. HARUT (203 Czech Republic), M. SCHULC (203 Czech Republic), V. KLUPÁK (203 Czech Republic), Zdeněk MATĚJ (203 Czech Republic, guarantor, belonging to the institution), František CVACHOVEC (203 Czech Republic), B. JÁNSKÝ (203 Czech Republic), E. NOVÁK (203 Czech Republic), T. CZAKOJ (203 Czech Republic), V. JUŘÍČEK (203 Czech Republic) and S. ZARITSKY (643 Russian Federation).
Edition Applied Radiation and Isotopes, Elsevier, 2018, 0969-8043.
Other information
Original language English
Type of outcome Article in a journal
Field of Study 10304 Nuclear physics
Country of publisher Netherlands
Confidentiality degree is not subject to a state or trade secret
WWW URL
Impact factor Impact factor: 1.343
RIV identification code RIV/00216224:14330/18:00103752
Organization unit Faculty of Informatics
Doi http://dx.doi.org/10.1016/j.apradiso.2018.09.005
UT WoS 000454462500003
Keywords in English VVER-1000; Mock-Up; LR-0; Reactor dosimetry; Neutron spectrometry; RPV
Changed by Changed by: RNDr. Pavel Šmerk, Ph.D., učo 3880. Changed: 29/4/2019 17:25.
Abstract
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.
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