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 |
| Publication status | Published - Dec 1 2001 |
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All Science Journal Classification (ASJC) codes
- Engineering(all)
Cite this
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, 01.12.2001, p. 753-757.Research output: Contribution to journal › Article
}
TY - JOUR
T1 - Studies on flibe blanket designs in helical reactor FFHR
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 - 2001/12/1
Y1 - 2001/12/1
N2 - 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.
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.
UR - http://www.scopus.com/inward/record.url?scp=6644224001&partnerID=8YFLogxK
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M3 - Article
AN - SCOPUS:6644224001
VL - 39
SP - 753
EP - 757
JO - Fusion Science and Technology
JF - Fusion Science and Technology
SN - 1536-1055
IS - 2
ER -