Control rod calibration simulation using Monte Carlo code for the IRT-type research reactor

Control rod calibration simulation using Monte Carlo code for the IRT-type research reactor

Detalles Bibliográficos
Parent link:Annals of Nuclear Energy
Vol. 96.— 2016.— [P. 332–343]
Autor Corporativo: Национальный исследовательский Томский политехнический университет Физико-технический институт Кафедра физико-энергетических установок (№ 21)
Outros autores: Shchurovskaya M. V. Mariya Vladimirovna, Alferov V. P. Vladimir Petrovich, Geraskin N. I. Nikolay Ivanovich, Radaev A. I. Aleksandr Ivanovich, Naymushin A. G. Artem Georgievich, Chertkov Yu. B. Yuri Borisovich, Anikin M. N. Mikhail Nikolaevich, Lebedev I. I. Ivan Igorevich
Summary:Title screen
This paper presents the results of the validation of a research reactor calculation using Monte Carlo code against experimental data. Validation efforts are carried out for two university-based research reactors in Russia: the IRT MEPhI reactor at the National Research Nuclear University MEPhI and the IRT-T reactor at the National Research Tomsk Polytechnic University. Calculations were performed using the continuous energy Monte Carlo code MCU-PTR. Full 3-D models for the IRT MEPhI and IRT-T reactors were developed. Measured critical cases during the control rod calibrations are analyzed in benchmarking studies. A procedure for the comparison of the measured and the calculated control rod worth based on the detailed calibration simulation is proposed.
Режим доступа: по договору с организацией-держателем ресурса
Idioma:inglés
Publicado: 2016
Subjects:
электронный ресурс
труды учёных ТПУ
исследовательский ядерный реактор
нейтроника
коды
стержни
калибровка
Acceso en liña:http://dx.doi.org/10.1016/j.anucene.2016.06.015
Formato: Electrónico Capítulo de libro
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=651476
Descripción
Summary:Title screen
This paper presents the results of the validation of a research reactor calculation using Monte Carlo code against experimental data. Validation efforts are carried out for two university-based research reactors in Russia: the IRT MEPhI reactor at the National Research Nuclear University MEPhI and the IRT-T reactor at the National Research Tomsk Polytechnic University. Calculations were performed using the continuous energy Monte Carlo code MCU-PTR. Full 3-D models for the IRT MEPhI and IRT-T reactors were developed. Measured critical cases during the control rod calibrations are analyzed in benchmarking studies. A procedure for the comparison of the measured and the calculated control rod worth based on the detailed calibration simulation is proposed.
Режим доступа: по договору с организацией-держателем ресурса
DOI:10.1016/j.anucene.2016.06.015

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