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High-temperature operation mode of HTTR for hydrogen production facility

Ho, H. Q.   ; 後藤 実  ; 長住 達; 石井 俊晃 ; 島崎 洋祐 ; Simanullang, I. L.* ; 藤本 望*; 石塚 悦男   ; 飯垣 和彦 

Ho, H. Q.; Goto, Minoru; Nagasumi, Satoru; Ishii, Toshiaki; Shimazaki, Yosuke; Simanullang, I. L.*; Fujimoto, Nozomu*; Ishitsuka, Etsuo; Iigaki, Kazuhiko

The conceptual design of a demonstration hydrogen production facility using heat supply from the high temperature engineering test reactor is being researched and developed at Japan Atomic Energy Agency. This facility produces hydrogen with a thermochemical water splitting Iodine-Sulphur process that requires high temperature heat to extract hydrogen efficiently. In order to achieve hydrogen with high efficiency, the helium outlet temperature should be as high as 950$$^{circ}$$C. Increasing the outlet temperature increases the reactor core temperature, and as a result the operation time decreases. If the operation time is reduced too much, it is not feasible to use the HTTR as a heat supply for the IS plant. Therefore, the purpose of this study is to estimate the operation time of the HTTR at high operation mode of 950$$^{circ}$$C to confirm whether it could supply long enough high temperature heat for the demonstration hydrogen IS plant. As result, the core temperature increase about by 50 to 100$$^{circ}$$C when the outlet temperature increases from 850 to 950$$^{circ}$$C. Although the increase of core temperature makes keff decrease by about 0.3 percent-delta-k per kelvin, the HTTR can still operate approximately 660EFPD. Therefore, it is possible to use the HTTR for long-term high-temperature heat supply to the demonstration hydrogen production IS plant.

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