Thermo-Physical Properties of Dispersion Nuclear Fuel for a New-Generation Reactors: A Computational Approach; AIP Conference Proceedings; Vol. 2101 : Isotopes: Technologies, Materials and Application (ITMA-2018)

Detaylı Bibliyografya
Parent link:AIP Conference Proceedings
Vol. 2101 : Isotopes: Technologies, Materials and Application (ITMA-2018).— 2019.— [020002, 7 p.]
Kurumsal yazarlar: Национальный исследовательский Томский политехнический университет Инженерная школа ядерных технологий Отделение ядерно-топливного цикла, Национальный исследовательский Томский политехнический университет Инженерная школа ядерных технологий Лаборатория плазменных гибридных систем, Национальный исследовательский Томский политехнический университет Инженерная школа ядерных технологий Научная лаборатория изотопного анализа и технологий
Diğer Yazarlar: Bedenko S. V. Sergey Vladimirovich, Karengin A. G. Aleksander Grigorievich, Nima Ghal-Eh, Alekseev N. Nikita, Knyshev V. V. Vladimir Vladimirovich, Shamanin I. V. Igor Vladimirovich
Özet:Title screen
Tomsk Polytechnic University is conducting a series of experiments to develop a nuclear fuel manufacturing technology required for a new-generation innovative nuclear systems. In this study, the thermal conductivity and thermophysical properties were calculated for the proposed nuclear fuel, which are necessary before proceeding to the construction stage. The cylindrical fuel compact consisting of spherical coated constituents (Pu,Th)O[2] of BISO type, were sintered together within a graphite matrix (C). Also, a composite material made of nuclear fuel (Pu,Th)O[2] and refractory oxides BeO/MgO, were prepared using plasma-chemical synthesis method. The development of a fuel pellet with desired physical properties that can be exposed for a long time under irradiation in a high-temperature gas-cooled thorium reactor core is the main technological advantage of the present study.
Режим доступа: по договору с организацией-держателем ресурса
Dil:İngilizce
Baskı/Yayın Bilgisi: 2019
Konular:
Online Erişim:https://doi.org/10.1063/1.5099594
Materyal Türü: Elektronik Kitap Bölümü
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=660276

MARC

LEADER 00000nla2a2200000 4500
001 660276
005 20251031112550.0
035 |a (RuTPU)RU\TPU\network\29397 
035 |a RU\TPU\network\29395 
090 |a 660276 
100 |a 20190522a2019 k y0engy50 ba 
101 0 |a eng 
105 |a y z 100zy 
135 |a drcn ---uucaa 
181 0 |a i  
182 0 |a b 
200 1 |a Thermo-Physical Properties of Dispersion Nuclear Fuel for a New-Generation Reactors: A Computational Approach  |f S. V. Bedenko [et al.] 
203 |a Text  |c electronic 
300 |a Title screen 
320 |a [References: 29 tit.] 
330 |a Tomsk Polytechnic University is conducting a series of experiments to develop a nuclear fuel manufacturing technology required for a new-generation innovative nuclear systems. In this study, the thermal conductivity and thermophysical properties were calculated for the proposed nuclear fuel, which are necessary before proceeding to the construction stage. The cylindrical fuel compact consisting of spherical coated constituents (Pu,Th)O[2] of BISO type, were sintered together within a graphite matrix (C). Also, a composite material made of nuclear fuel (Pu,Th)O[2] and refractory oxides BeO/MgO, were prepared using plasma-chemical synthesis method. The development of a fuel pellet with desired physical properties that can be exposed for a long time under irradiation in a high-temperature gas-cooled thorium reactor core is the main technological advantage of the present study. 
333 |a Режим доступа: по договору с организацией-держателем ресурса 
461 0 |0 (RuTPU)RU\TPU\network\4816  |t AIP Conference Proceedings 
463 0 |0 (RuTPU)RU\TPU\network\29393  |t Vol. 2101 : Isotopes: Technologies, Materials and Application (ITMA-2018)  |o V International Conference for Young Scientists, Post-Graduate Students and Students, 19-23 November 2018, Tomsk, Russia  |o [proceedings]  |f National Research Tomsk Polytechnic University (TPU) ; eds. G. A. Martoyan, A. Yu. Godymchuk (Godimchuk), L. Rieznichenko  |v [020002, 7 p.]  |d 2019 
610 1 |a электронный ресурс 
610 1 |a труды учёных ТПУ 
610 1 |a теплофизические свойства 
610 1 |a ядерное топливо 
610 1 |a дисперсионное топливо 
610 1 |a реакторы 
610 1 |a инновационные системы 
610 1 |a теплопроводность 
610 1 |a теплофизические свойства 
610 1 |a топливные таблетки 
610 1 |a ториевые реакторы 
610 1 |a облучение 
701 1 |a Bedenko  |b S. V.  |c physicist  |c Associate Professor of Tomsk Polytechnic University, Candidate of physical and mathematical sciences  |f 1980-  |g Sergey Vladimirovich  |3 (RuTPU)RU\TPU\pers\30831  |9 15078 
701 1 |a Karengin  |b A. G.  |c physicist  |c Associate Professor of Tomsk Polytechnic University, Candidate of physical and mathematical sciences  |f 1950-  |g Aleksander Grigorievich  |3 (RuTPU)RU\TPU\pers\31220 
701 0 |a Nima Ghal-Eh 
701 1 |a Alekseev  |b N.  |g Nikita 
701 1 |a Knyshev  |b V. V.  |c physicist  |c engineer-researcher of Tomsk Polytechnic University  |f 1993-  |g Vladimir Vladimirovich  |3 (RuTPU)RU\TPU\pers\37379  |9 20297 
701 1 |a Shamanin  |b I. V.  |c specialist in the field of nuclear physics  |c Professor of Tomsk Polytechnic University, Doctor of physical and mathematical sciences  |c specialist in the field of nuclear power engineering  |f 1962-  |g Igor Vladimirovich  |3 (RuTPU)RU\TPU\pers\30832 
712 0 2 |a Национальный исследовательский Томский политехнический университет  |b Инженерная школа ядерных технологий  |b Отделение ядерно-топливного цикла  |3 (RuTPU)RU\TPU\col\23554 
712 0 2 |a Национальный исследовательский Томский политехнический университет  |b Инженерная школа ядерных технологий  |b Лаборатория плазменных гибридных систем  |3 (RuTPU)RU\TPU\col\23381 
712 0 2 |a Национальный исследовательский Томский политехнический университет  |b Инженерная школа ядерных технологий  |b Научная лаборатория изотопного анализа и технологий  |3 (RuTPU)RU\TPU\col\25157 
801 2 |a RU  |b 63413507  |c 20190522  |g RCR 
856 4 |u https://doi.org/10.1063/1.5099594 
942 |c CF