Degradation of Beryllium Reflector Properties on the IRT-T Reactor
| Parent link: | Advanced Materials Research : Radiation and nuclear techniques in material science: Scientific Journal Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014).— 2015.— [P. 289-293] |
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| Kurumsal yazarlar: | , , |
| Diğer Yazarlar: | , , , , , |
| Özet: | Title screen This paper presents the results of a numerical calculation of beryllium poisoning of an IRT-T reactor and its effect on the excess reactivity and neutron flux density in the beam ports. Also, the prediction of {6}Li and{3}He poison concentrations in the beryllium reflectors of the IRT-T reactor is presented. The results are based on MCU Monte Carlo calculations. The part of reactor history was taken into account to predict reliable values of parasitic isotope concentrations. The impact of shut-down time and operating time on the excess reactivity is shown. The results presented in this paper could be used to perform the safety analysis of an IRT-T reactor. Режим доступа: по договору с организацией-держателем ресурса |
| Dil: | İngilizce |
| Baskı/Yayın Bilgisi: |
2015
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| Seri Bilgileri: | Nuclear Engineering and Fuel Cycles |
| Konular: | |
| Online Erişim: | http://dx.doi.org/10.4028/www.scientific.net/AMR.1084.289 |
| Materyal Türü: | Elektronik Kitap Bölümü |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=640323 |
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| 200 | 1 | |a Degradation of Beryllium Reflector Properties on the IRT-T Reactor |f A. G. Naymushin [et al.] | |
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| 225 | 1 | |a Nuclear Engineering and Fuel Cycles | |
| 300 | |a Title screen | ||
| 330 | |a This paper presents the results of a numerical calculation of beryllium poisoning of an IRT-T reactor and its effect on the excess reactivity and neutron flux density in the beam ports. Also, the prediction of {6}Li and{3}He poison concentrations in the beryllium reflectors of the IRT-T reactor is presented. The results are based on MCU Monte Carlo calculations. The part of reactor history was taken into account to predict reliable values of parasitic isotope concentrations. The impact of shut-down time and operating time on the excess reactivity is shown. The results presented in this paper could be used to perform the safety analysis of an IRT-T reactor. | ||
| 333 | |a Режим доступа: по договору с организацией-держателем ресурса | ||
| 461 | 1 | |0 (RuTPU)RU\TPU\network\4598 |t Advanced Materials Research : Radiation and nuclear techniques in material science |o Scientific Journal | |
| 463 | 1 | |0 (RuTPU)RU\TPU\network\4600 |t Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014) |o The VIth International Conference, June 5-7, 2014, Tomsk, Russia |o [proceedings] |f National Research Tomsk Polytechnic University (TPU) |v [P. 289-293] |d 2015 | |
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