Studies on flibe blanket designs in helical reactor FFHR

Akio Sagara; Hirokuni Yamanishi; Tatsuhiko Uda; Osamu Motojima; Osamu Mitarai; Tomoaki Kunugi; Youji Matsumoto; Shin Ichi Satake; Yican Wu; Takayuki Terai; Satoru Tanaka; Hideki Matsui; Shintaro Takahasi; Takuya Yamamoto; Saburo Toda; Satoshi Fukada; Masabumi Nishikawa; Akihiko Shimizu; Naoaki Yoshida

doi:10.13182/fst01-a11963329

Studies on flibe blanket designs in helical reactor FFHR

Akio Sagara, Hirokuni Yamanishi, Tatsuhiko Uda, Osamu Motojima, Osamu Mitarai, Tomoaki Kunugi, Youji Matsumoto, Shin Ichi Satake, Yican Wu, Takayuki Terai, Satoru Tanaka, Hideki Matsui, Shintaro Takahasi, Takuya Yamamoto, Saburo Toda, Satoshi Fukada, Masabumi Nishikawa, Akihiko Shimizu, Naoaki Yoshida

Engineering Science for Advanced energy system

Research output: Contribution to journal › Article › peer-review

35 Citations (Scopus)

Abstract

The self-cooling molten-salt Flibe blanket of FFHR is numerically analyzed, resulting the optimum first wall to be as thin as 5mm and the heat flux up to 0.25MW/m² to be feasible with adopting V-4Cr-4Ti as the structural material. An alternative concept of free surface using a capillary force is shown to be feasible even in helical systems, where a spiral flow is formed and drastically enhances the heat transfer efficiency. The nuclear property of Flibe blanket is modified with increasing Be amount and adopting carbon reflector, resulting the local TBR of 1.3. As an optional technique, 50% enrichment of Li-6 gives the maximum TBR of 1.4.

Original language	English
Pages (from-to)	753-757
Number of pages	5
Journal	Fusion Technology
Volume	39
Issue number	2
DOIs	https://doi.org/10.13182/fst01-a11963329
Publication status	Published - 2001

All Science Journal Classification (ASJC) codes

Engineering(all)

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Sagara, A., Yamanishi, H., Uda, T., Motojima, O., Mitarai, O., Kunugi, T., Matsumoto, Y., Satake, S. I., Wu, Y., Terai, T., Tanaka, S., Matsui, H., Takahasi, S., Yamamoto, T., Toda, S., Fukada, S., Nishikawa, M., Shimizu, A., & Yoshida, N. (2001). Studies on flibe blanket designs in helical reactor FFHR. Fusion Technology, 39(2), 753-757. https://doi.org/10.13182/fst01-a11963329

Studies on flibe blanket designs in helical reactor FFHR. / Sagara, Akio; Yamanishi, Hirokuni; Uda, Tatsuhiko; Motojima, Osamu; Mitarai, Osamu; Kunugi, Tomoaki; Matsumoto, Youji; Satake, Shin Ichi; Wu, Yican; Terai, Takayuki; Tanaka, Satoru; Matsui, Hideki; Takahasi, Shintaro; Yamamoto, Takuya; Toda, Saburo; Fukada, Satoshi; Nishikawa, Masabumi; Shimizu, Akihiko; Yoshida, Naoaki.

In: Fusion Technology, Vol. 39, No. 2, 2001, p. 753-757.

Research output: Contribution to journal › Article › peer-review

Sagara, A, Yamanishi, H, Uda, T, Motojima, O, Mitarai, O, Kunugi, T, Matsumoto, Y, Satake, SI, Wu, Y, Terai, T, Tanaka, S, Matsui, H, Takahasi, S, Yamamoto, T, Toda, S, Fukada, S, Nishikawa, M, Shimizu, A & Yoshida, N 2001, 'Studies on flibe blanket designs in helical reactor FFHR', Fusion Technology, vol. 39, no. 2, pp. 753-757. https://doi.org/10.13182/fst01-a11963329

Sagara, Akio ; Yamanishi, Hirokuni ; Uda, Tatsuhiko ; Motojima, Osamu ; Mitarai, Osamu ; Kunugi, Tomoaki ; Matsumoto, Youji ; Satake, Shin Ichi ; Wu, Yican ; Terai, Takayuki ; Tanaka, Satoru ; Matsui, Hideki ; Takahasi, Shintaro ; Yamamoto, Takuya ; Toda, Saburo ; Fukada, Satoshi ; Nishikawa, Masabumi ; Shimizu, Akihiko ; Yoshida, Naoaki. / Studies on flibe blanket designs in helical reactor FFHR. In: Fusion Technology. 2001 ; Vol. 39, No. 2. pp. 753-757.

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abstract = "The self-cooling molten-salt Flibe blanket of FFHR is numerically analyzed, resulting the optimum first wall to be as thin as 5mm and the heat flux up to 0.25MW/m2 to be feasible with adopting V-4Cr-4Ti as the structural material. An alternative concept of free surface using a capillary force is shown to be feasible even in helical systems, where a spiral flow is formed and drastically enhances the heat transfer efficiency. The nuclear property of Flibe blanket is modified with increasing Be amount and adopting carbon reflector, resulting the local TBR of 1.3. As an optional technique, 50% enrichment of Li-6 gives the maximum TBR of 1.4.",

author = "Akio Sagara and Hirokuni Yamanishi and Tatsuhiko Uda and Osamu Motojima and Osamu Mitarai and Tomoaki Kunugi and Youji Matsumoto and Satake, {Shin Ichi} and Yican Wu and Takayuki Terai and Satoru Tanaka and Hideki Matsui and Shintaro Takahasi and Takuya Yamamoto and Saburo Toda and Satoshi Fukada and Masabumi Nishikawa and Akihiko Shimizu and Naoaki Yoshida",

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AU - Sagara, Akio

AU - Yamanishi, Hirokuni

AU - Uda, Tatsuhiko

AU - Motojima, Osamu

AU - Mitarai, Osamu

AU - Kunugi, Tomoaki

AU - Matsumoto, Youji

AU - Satake, Shin Ichi

AU - Wu, Yican

AU - Terai, Takayuki

AU - Tanaka, Satoru

AU - Matsui, Hideki

AU - Takahasi, Shintaro

AU - Yamamoto, Takuya

AU - Toda, Saburo

AU - Fukada, Satoshi

AU - Nishikawa, Masabumi

AU - Shimizu, Akihiko

AU - Yoshida, Naoaki

PY - 2001

Y1 - 2001

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AB - The self-cooling molten-salt Flibe blanket of FFHR is numerically analyzed, resulting the optimum first wall to be as thin as 5mm and the heat flux up to 0.25MW/m2 to be feasible with adopting V-4Cr-4Ti as the structural material. An alternative concept of free surface using a capillary force is shown to be feasible even in helical systems, where a spiral flow is formed and drastically enhances the heat transfer efficiency. The nuclear property of Flibe blanket is modified with increasing Be amount and adopting carbon reflector, resulting the local TBR of 1.3. As an optional technique, 50% enrichment of Li-6 gives the maximum TBR of 1.4.

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Studies on flibe blanket designs in helical reactor FFHR

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