Preliminary core and fuel design of bwr with multi-Axial fuel shuffling

Yudai Tasaki, Akifumi Yamaji

研究成果: Conference contribution

抄録

The concept of "multi-Axial fuel shuffling" has been recently proposed for a high breeding core design of supercritical-water cooled reactor. In this study, the same design principle is applied to boiling water reactor (BWR) condition. The results show that the Compound System Doubling Time (CSDT) can be reduced by increasing fuel batch number of the upper blanket layer, but more investigations may be necessary to consider further improvement of the core breeding performance. Moreover, fuel performance of the axially heterogeneous core has been evaluated with the power history obtained by the core calculations and modified FEMAXI-7 code which consider two different types of pellets (i.e., MOX and depleted uranium) within one fuel rod. The analysis results indicate that uncertainty in thermal conductivity of MOX pellets may be important in evaluating the peak pellet temperature, while relatively large plenum volume may be required at the bottom of the fuel rod to accommodate the large amount of fission gas release. Another potential design issue may be the cladding outer diameter increase by the MOX pellet swelling, which may have significant influence on evaluation of MCHFR.

本文言語English
ホスト出版物のタイトルProceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018
出版社American Nuclear Society
ページ1144-1152
ページ数9
ISBN(電子版)9780894487552
出版ステータスPublished - 2018
イベント2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018 - Charlotte, United States
継続期間: 2018 4 82018 4 11

出版物シリーズ

名前Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018

Other

Other2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018
国/地域United States
CityCharlotte
Period18/4/818/4/11

ASJC Scopus subject areas

  • エネルギー工学および電力技術
  • 原子力エネルギーおよび原子力工学

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