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

Research output: Contribution to journalArticlepeer-review

37 Citations (Scopus)


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 languageEnglish
Pages (from-to)753-757
Number of pages5
JournalFusion Technology
Issue number2
Publication statusPublished - 2001

All Science Journal Classification (ASJC) codes

  • Engineering(all)


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