Gas-cooled thorium reactor with fuel block of the unified design / I. V. Shamanin [et al.]

Уровень набора: Nuclear Energy and Technology = 2015-Альтернативный автор-лицо: Shamanin, I. V., specialist in the field of nuclear physics, Professor of Tomsk Polytechnic University, Doctor of physical and mathematical sciences, specialist in the field of nuclear power engineering, 1962-, Igor Vladimirovich;Chertkov, Yu. B., physicist, Associate Professor of Tomsk Polytechnic University, Candidate of physical and mathematical sciences, 1948-, Yuri Borisovich;Bedenko, S. V., physicist, Associate Professor of Tomsk Polytechnic University, Candidate of physical and mathematical sciences, 1980-, Sergey Vladimirovich;Gubaydulin, I. M., Ildar MukharamovichКоллективный автор (вторичный): Национальный исследовательский Томский политехнический университет (ТПУ), Физико-технический институт (ФТИ), Кафедра технической физики (№ 23) (ТФ);Национальный исследовательский Томский политехнический университет (ТПУ), Физико-технический институт (ФТИ), Кафедра физико-энергетических установок (№ 21) (ФЭУ)Язык: английский.Резюме или реферат: Scientific investigation aimed at the implementation of advance technological platform is carried out in Russia based on the ideas of nuclear fuel breeding within closed fuel cycle and on the physical principles of fast reactors. Innovation design of low-power reactor facilities also fall under the new technological platform. High-temperature gas-cooled nuclear reactors operated with thorium fuel load possessing advantageous features of transportability, factory prefabricated manufacturing, short on-site assembly and start-up period and ability to work during extended time periods without fuel reloading represent promising direction of development in this area of nuclear power generation. It is specifically this type of low-power nuclear reactors brought to commercially competitive level that must form the basis of regional power generation in Russia. The objective of the present study is to develop the concept of low-power inherently safe thorium-fueled nuclear power installation based on the unified design of the fuel block..Примечания о наличии в документе библиографии/указателя: [References: р. 189-190 (17 tit.)].Аудитория: .Тематика: электронный ресурс | труды учёных ТПУ Ресурсы он-лайн:Щелкните здесь для доступа в онлайн
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[References: р. 189-190 (17 tit.)]

Scientific investigation aimed at the implementation of advance technological platform is carried out in Russia based on the ideas of nuclear fuel breeding within closed fuel cycle and on the physical principles of fast reactors. Innovation design of low-power reactor facilities also fall under the new technological platform. High-temperature gas-cooled nuclear reactors operated with thorium fuel load possessing advantageous features of transportability, factory prefabricated manufacturing, short on-site assembly and start-up period and ability to work during extended time periods without fuel reloading represent promising direction of development in this area of nuclear power generation. It is specifically this type of low-power nuclear reactors brought to commercially competitive level that must form the basis of regional power generation in Russia. The objective of the present study is to develop the concept of low-power inherently safe thorium-fueled nuclear power installation based on the unified design of the fuel block.

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