Publication:
Simulation-based studies on graphite absorption properties for ASTRA critical experiments

Дата
2022
Авторы
Nevinitsa, V. A.
Fomichenko, P. A.
Jitarev, V. E.
Shchurovskaya, M. V.
Kruglikov, A. E.
Volkov, Y. N.
Geraskin, N. I.
Кругликов, Антон Евгеньевич
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Организационные подразделения
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Организационная единица
Институт ядерной физики и технологий
Цель ИЯФиТ и стратегия развития - создание и развитие научно-образовательного центра мирового уровня в области ядерной физики и технологий, радиационного материаловедения, физики элементарных частиц, астрофизики и космофизики.
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Аннотация
© 2022 Elsevier LtdThis work is focused on the improvement of the graphite impurity content characterization for the ASTRA critical facility. The equivalent boron content for the graphite reflectors of the ASTRA facility reported in the benchmark specifications was estimated using the results of the exponential experiments performed by graphite manufacturer. Because raw measured data are not available for these experiments, we tried to reassess the equivalent boron content for the ASTRA graphite reflectors using the results of analogous exponential experiments performed earlier on the empty RBMK critical facility at the National Research Center «Kurchatov Institute» and further simulation of the experiments utilizing the Monte Carlo code Serpent with ENDF/B-VII.0, ENDF/B-VII.1, and ENDF/B-VIII.0 cross-section libraries. The same grade graphite was used for manufacturing the graphite blocks for the RBMK critical facility and the ASTRA critical facility. The Monte Carlo simulations confirmed the accuracy of the exponential measurements performed for RBMK graphite characterization. It was also shown that the simulation must reproduce the graphite absorption cross-section estimated using the exponential experiments for the agreement between the measured and calculated distribution of thermal neutron flux. Therefore, the equivalent boron content should be assessed individually for each cross-section library used in the simulation. In case of the ASTRA facility the carbon capture cross section of 3.36 mb at 0.0253 eV (ENDF/B-VII.0) was used to deduce the equivalent boron content of 1 ppm wt from the measured results. Thermal capture cross-section of carbon was significantly increased in the ENDF/B-VII.1 and other recent cross-section libraries. Therefore, when calculating the ASTRA benchmark with these cross-section libraries the equivalent boron content reported in the benchmark specification should be reassessed.
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Simulation-based studies on graphite absorption properties for ASTRA critical experiments / Nevinitsa, V.A. [et al.] // Annals of Nuclear Energy. - 2022. - 170. - 10.1016/j.anucene.2022.109013
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https://www.doi.org/10.1016/j.anucene.2022.109013
 https://www.scopus.com/record/display.uri?eid=2-s2.0-85124581641&origin=resultslist
 http://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcAuth=Alerting&SrcApp=Alerting&DestApp=WOS_CPL&DestLinkType=FullRecord&UT=WOS:000793203800005
 https://openrepository.mephi.ru/handle/123456789/28751
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