2018年7月1日
Initial relocation behavior of control rod materials in boiling water reactors studied via time-resolved visualization
Nuclear Engineering and Design
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- 巻
- 333
- 号
- 開始ページ
- 99
- 終了ページ
- 114
- 記述言語
- 英語
- 掲載種別
- 研究論文(学術雑誌)
- DOI
- 10.1016/j.nucengdes.2018.04.006
- 出版者・発行元
- Elsevier Ltd
For the Fukushima decommissioning, the distribution of boron species in the fuel debris must be determined to assess the risk of recriticality, the debris hardness and thus complicate its successful retrieval. As a result, the relocation behavior of boron carbide (B4C) control rod materials has attracted significant attention. In this work, the influence of the thickness of its stainless steel (SS) clad on the initial relocation behavior of the control rod was investigated. In particular, the initial relocation behavior of the B4C control rod materials was dynamically visualized using a technique previously developed by the authors. To simulate the control rod, a type-304 SS tube filled with B4C powder containing particles with sizes of approximately 20–30 µm was heated to a temperature exceeding its eutectic point (1473 K). The three relocation modes of the obtained eutectic melt corresponded to film formation, droplet formation without collapse and droplet formation with collapse.
- リンク情報
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- DOI
- https://doi.org/10.1016/j.nucengdes.2018.04.006
- Web of Science
- https://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcAuth=JSTA_CEL&SrcApp=J_Gate_JST&DestLinkType=FullRecord&KeyUT=WOS:000432753200009&DestApp=WOS_CPL
- URL
- http://www.scopus.com/inward/record.url?eid=2-s2.0-85045754628&partnerID=MN8TOARS
- URL
- http://orcid.org/0000-0001-9868-4305
- Scopus Citedby
- https://www.scopus.com/inward/citedby.uri?partnerID=HzOxMe3b&scp=85045754628&origin=inward
- ID情報
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- DOI : 10.1016/j.nucengdes.2018.04.006
- ISSN : 0029-5493
- ORCIDのPut Code : 57422601
- SCOPUS ID : 85045754628
- Web of Science ID : WOS:000432753200009