Title of article
Performance of high-temperature gas-cooled reactor as a tritium production device for fusion reactors
Author/Authors
Matsuura، نويسنده , , H. and Kouchi، نويسنده , , S. and Nakaya، نويسنده , , H. and Yasumoto، نويسنده , , T. and Nakao، نويسنده , , Y. and Shimakawa، نويسنده , , S. and Goto، نويسنده , , M. and Nakagawa، نويسنده , , S. and Nishikawa، نويسنده , , M.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2012
Pages
7
From page
95
To page
101
Abstract
The performance of a high-temperature gas-cooled reactor as a tritium production device is examined. A gas turbine high-temperature reactor of 300 MWe nominal capacity (GTHTR300) is assumed as the calculation target of a typical gas-cooled reactor, and using the continuous-energy Monte Carlo transport code MVP-BURN, burn-up simulations for the 3-dimensional entire-core region of GTHTR300 were carried out considering its unique double heterogeneity structure. It is shown that gas-cooled reactors with thermal output power of 3 GW in all can produce 5–8 kg of tritium in a year.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2012
Journal title
Nuclear Engineering and Design Eslah
Record number
1591911
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