Control rod calibration simulation using Monte Carlo code for the IRT-type research reactor; Annals of Nuclear Energy; Vol. 96

Chi tiết về thư mục
Parent link:Annals of Nuclear Energy
Vol. 96.— 2016.— [P. 332–343]
Tác giả của công ty: Национальный исследовательский Томский политехнический университет Физико-технический институт Кафедра физико-энергетических установок (№ 21)
Tác giả khác: 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
Tóm tắt: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
Ngôn ngữ:Tiếng Anh
Được phát hành: 2016
Những chủ đề:
Truy cập trực tuyến:http://dx.doi.org/10.1016/j.anucene.2016.06.015
Định dạng: Điện tử Chương của sách
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=651476

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