The effect of local power increase on neutron flux in internal
parts of the VVER-1000 Mock-Up in LR-0 reactor

J 2018

The effect of local power increase on neutron flux in internal parts of the VVER-1000 Mock-Up in LR-0 reactor

KOŠŤÁL, M., E. LOSA, M. SCHULC, J. ŠIMON, D. HARUT et. al.

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

Language

English

Type of outcome

Článek v odborném periodiku

Field of Study

10304 Nuclear physics

Country of publisher

Netherlands

Confidentiality degree

není předmětem státního či obchodního tajemství

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

Změněno: 29/4/2019 15:37, RNDr. Pavel Šmerk, Ph.D.

Abstract

V originále

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.

Citovat

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.

@article{1439807,
   author = {Košťál, M. and Losa, E. and Schulc, M. and Šimon, J. and Harut, D. and Klupák, V. and Czakoj, T. and Juříček, V. and Matěj, Zdeněk and Cvachovec, František and Rypar, V.},
   article_number = {November},
   doi = {http://dx.doi.org/10.1016/j.anucene.2018.08.007},
   keywords = {LR-0; Neutron spectrometry; Reactor dosimetry; VVER-1000; Mock-Up},
   language = {eng},
   issn = {0306-4549},
   journal = {Annals of Nuclear Energy},
   title = {The effect of local power increase on neutron flux in internal parts of the VVER-1000 Mock-Up in LR-0 reactor},
   volume = {121},
   year = {2018}
}

TY  - JOUR
ID  - 1439807
AU  - Košťál, M. - Losa, E. - Schulc, M. - Šimon, J. - Harut, D. - Klupák, V. - Czakoj, T. - Juříček, V. - Matěj, Zdeněk - Cvachovec, František - Rypar, V.
PY  - 2018
TI  - The effect of local power increase on neutron flux in internal parts of the VVER-1000 Mock-Up in LR-0 reactor
JF  - Annals of Nuclear Energy
VL  - 121
IS  - November
SP  - 567-576
EP  - 567-576
SN  - 03064549
KW  - LR-0
KW  - Neutron spectrometry
KW  - Reactor dosimetry
KW  - VVER-1000
KW  - Mock-Up
N2  - 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.
ER  -

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. \textit{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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