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

Research output: Contribution to journalArticlepeer-review

8 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 languageEnglish
Pages (from-to)1667-1669
Number of pages3
JournalFusion Engineering and Design
Volume87
Issue number9
DOIs
Publication statusPublished - 2012 Sep 1
Externally publishedYes

Keywords

  • ANIHEAT
  • Solid blanket
  • TBR
  • Water-cooled

ASJC Scopus subject areas

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

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