KOŠŤÁL, M., E. LOSA, M. SCHULC, J. ŠIMON, D. HARUT, V. KLUPÁK, T. CZAKOJ, V. JUŘÍČEK, Zdeněk MATĚJ, František CVACHOVEC and V. RYPAR. The effect of local power increase on neutron flux in internal parts of the VVER-1000 Mock-Up in LR-0 reactor. Annals of Nuclear Energy. 2018, vol. 121, November, p. 567-576. ISSN 0306-4549. Available from: https://dx.doi.org/10.1016/j.anucene.2018.08.007.
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Basic information
Original name The effect of local power increase on neutron flux in internal parts of the VVER-1000 Mock-Up in LR-0 reactor
Authors KOŠŤÁL, M. (203 Czech Republic), E. LOSA (203 Czech Republic), M. SCHULC (203 Czech Republic), J. ŠIMON (203 Czech Republic), D. HARUT (203 Czech Republic), V. KLUPÁK (203 Czech Republic), T. CZAKOJ (203 Czech Republic), V. JUŘÍČEK (203 Czech Republic), Zdeněk MATĚJ (203 Czech Republic, guarantor, belonging to the institution), František CVACHOVEC (203 Czech Republic) and V. RYPAR (203 Czech Republic).
Edition Annals of Nuclear Energy, 2018, 0306-4549.
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
Impact factor Impact factor: 1.380
RIV identification code RIV/00216224:14330/18:00103750
Organization unit Faculty of Informatics
Doi http://dx.doi.org/10.1016/j.anucene.2018.08.007
UT WoS 000444668200054
Keywords in English LR-0; Neutron spectrometry; Reactor dosimetry; VVER-1000; Mock-Up
Changed by Changed by: RNDr. Pavel Šmerk, Ph.D., učo 3880. Changed: 29/4/2019 15:37.
Abstract
The neutron flux distribution in the internal parts of a reactor is an important parameter which affects the absorbed dose, temperature, and gas production in the materials. Therefore, the knowledge of neutron flux distribution, for example in the baffle, is important for estimation of the radiation-induced swelling and activation of this internal component. The power distribution in the periphery fuel assemblies, mostly the lateral 2–3 pin rows, has considerable influence on neutron and gamma flux in the internal reactor elements. The power distribution in the core is mostly calculated by the reactor operator using diffusion codes. These data are used as an input for transport calculations, e.g., with Monte Carlo for the fluences, displacements per atoms, gamma heating and other important values for radiation damage estimation. This paper aims to compare the experimental and calculated reaction rate distribution in a mock-up of VVER-1000 (VVER-1000 Mock-Up) internals placed in the LR- 0 reactor and compares these quantities in case of a partial change of enrichment in one fuel assembly adjacent to the baffle simulator.
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