Influence of the Graphite’s Lifespan on the Design Value of Fuel Burnup in High Temperature Gas-Cooled Reactors; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)
| 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. 313-316] |
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| 団体著者: | |
| その他の著者: | , , , , , |
| 要約: | Title screen This paper describes a method of determining the correlation of the exhausted graphite fuel blocks’ lifespan in high temperature gas-cooled reactors with the fuel burnup. The axial distribution of the local values of the exhausted lifespan of graphite fuel blocks was obtained. It is shown that for ensuring the compliance of the design value of the fuel burnup with graphite fuel blocks operability, it is necessary to reduce the average mixed temperature of the helium coolant leaving the reactor core and as well as reduce the time between nuclear fuel recharges. Режим доступа: по договору с организацией-держателем ресурса |
| 言語: | 英語 |
| 出版事項: |
2015
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| シリーズ: | Nuclear Engineering and Fuel Cycles |
| 主題: | |
| オンライン･アクセス: | http://dx.doi.org/10.4028/www.scientific.net/AMR.1084.313 |
| 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=640332 |