Gas-cooled thorium reactor with fuel block of the unified design
| Parent link: | Nuclear Energy and Technology.— , 2015- Vol. 1, iss. 1.— 2016.— [P. 184–190] |
|---|---|
| 団体著者: | Национальный исследовательский Томский политехнический университет |
| その他の著者: | Shamanin I. V. Igor Vladimirovich, Chertkov Yu. B. Yuri Borisovich, Bedenko S. V. Sergey Vladimirovich, Gubaydulin I. M. Ildar Mukharamovich |
| 要約: | Title screen 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. Режим доступа: по договору с организацией-держателем ресурса |
| 言語: | 英語 |
| 出版事項: |
2016
|
| 主題: | |
| オンライン・アクセス: | http://dx.doi.org/10.1016/j.nucet.2016.01.012 |
| フォーマット: | 電子媒体 図書の章 |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=650571 |
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