TBR comparison of water-cooled blanket based on PWR and SCWR water conditions

C. Liu; K. Tobita; Y. Someya; H. Utoh; H. Takase; N. Asakura

doi:10.1016/j.fusengdes.2012.07.001

TBR comparison of water-cooled blanket based on PWR and SCWR water conditions

C. Liu, K. Tobita, Y. Someya, H. Utoh, H. Takase, N. Asakura

ENG - Quantum Science and Energy Engineering

Japan Atomic Energy Agency

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

9 Citations (Scopus)

Abstract

Nuclear analysis results were compared for water-cooled blanket based on PWR (pressurized water reactor) and SCWR (sub-critical water reactor) water conditions. The local TBR (tritium breeding ratio) in outboard zone was discussed in the range of P _n (neutron wall load) from 1 MW/m ² to 5 MW/m ². It was found that water fraction has little impact on TBR, which is an important factor related to blanket tritium efficiency. It indicated that TBR value of each P _n would be similar under the two kinds of water conditions, but PWR case is a little higher than that of SCWR's. In addition, it was found that beryllium is the dominant factor leading a higher TBR inside blanket. As a result, TBR is an insensitive value with the water condition variation. The results would be important to water condition choice for solid blanket in the future.

Original language	English
Pages (from-to)	1667-1669
Number of pages	3
Journal	Fusion Engineering and Design
Volume	87
Issue number	9
DOIs	https://doi.org/10.1016/j.fusengdes.2012.07.001
Publication status	Published - 2012 Sept

Keywords

ANIHEAT
Solid blanket
TBR
Water-cooled

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10.1016/j.fusengdes.2012.07.001

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title = "TBR comparison of water-cooled blanket based on PWR and SCWR water conditions",

abstract = "Nuclear analysis results were compared for water-cooled blanket based on PWR (pressurized water reactor) and SCWR (sub-critical water reactor) water conditions. The local TBR (tritium breeding ratio) in outboard zone was discussed in the range of P n (neutron wall load) from 1 MW/m 2 to 5 MW/m 2. It was found that water fraction has little impact on TBR, which is an important factor related to blanket tritium efficiency. It indicated that TBR value of each P n would be similar under the two kinds of water conditions, but PWR case is a little higher than that of SCWR's. In addition, it was found that beryllium is the dominant factor leading a higher TBR inside blanket. As a result, TBR is an insensitive value with the water condition variation. The results would be important to water condition choice for solid blanket in the future.",

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author = "C. Liu and K. Tobita and Y. Someya and H. Utoh and H. Takase and N. Asakura",

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T1 - TBR comparison of water-cooled blanket based on PWR and SCWR water conditions

AU - Liu, C.

AU - Tobita, K.

AU - Someya, Y.

AU - Utoh, H.

AU - Takase, H.

AU - Asakura, N.

PY - 2012/9

Y1 - 2012/9

N2 - Nuclear analysis results were compared for water-cooled blanket based on PWR (pressurized water reactor) and SCWR (sub-critical water reactor) water conditions. The local TBR (tritium breeding ratio) in outboard zone was discussed in the range of P n (neutron wall load) from 1 MW/m 2 to 5 MW/m 2. It was found that water fraction has little impact on TBR, which is an important factor related to blanket tritium efficiency. It indicated that TBR value of each P n would be similar under the two kinds of water conditions, but PWR case is a little higher than that of SCWR's. In addition, it was found that beryllium is the dominant factor leading a higher TBR inside blanket. As a result, TBR is an insensitive value with the water condition variation. The results would be important to water condition choice for solid blanket in the future.

AB - Nuclear analysis results were compared for water-cooled blanket based on PWR (pressurized water reactor) and SCWR (sub-critical water reactor) water conditions. The local TBR (tritium breeding ratio) in outboard zone was discussed in the range of P n (neutron wall load) from 1 MW/m 2 to 5 MW/m 2. It was found that water fraction has little impact on TBR, which is an important factor related to blanket tritium efficiency. It indicated that TBR value of each P n would be similar under the two kinds of water conditions, but PWR case is a little higher than that of SCWR's. In addition, it was found that beryllium is the dominant factor leading a higher TBR inside blanket. As a result, TBR is an insensitive value with the water condition variation. The results would be important to water condition choice for solid blanket in the future.

KW - ANIHEAT

KW - Solid blanket

KW - TBR

KW - Water-cooled

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JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

IS - 9

ER -

TBR comparison of water-cooled blanket based on PWR and SCWR water conditions

Abstract

Keywords

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