Evaluation of tritium release into primary coolant for research and testing reactors-Reference-Cited by-同舟云学术

Evaluation of tritium release into primary coolant for research and testing reactors

Published:2020-07-14 Issue:1 Volume:58 Page:1-8
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Kenzhina Inesh¹^ORCID,Ishitsuka Etsuo²,Okumura Keisuke³,Ho Hai Quan²^ORCID,Takemoto Noriyuki²,Chikhray Yevgeni¹

Affiliation:

1. Institute of Experimental and Theoretical Physics, Al-Farabi Kazakh National University, Almaty, Kazakhstan

2. Oarai Research and Development Institute, Sector of Fast Reactor and Advanced Reactor Research and Development Japan Atomic Energy Agency, Ibaraki, Japan

3. Collaborative Laboratories for Advanced Decommissioning Science, Sector of Fukushima Research and Development Japan Atomic Energy Agency, Fukushima, Japan

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00223131.2020.1791760

Reference24 articles.

1. Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors: Status, Challenges, and Path Forward

2. IAEA research reactor database [Internet]. IAEA. [cited 2020 Feb 17]. Available from: https://nucleus.iaea.org/RRDB/RR/ReactorSearch.aspx

3. Department of Research Reactor. Annual report of department of research reactor, 1991 (April 1, 1991~March 31, 1992). Japan: Japan Atomic Energy Research Institute; 1992, JAERI-M 92-154 [in Japanese].

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