Absolute quantification of <sup>137</sup>Cs activity in spent nuclear fuel with calculated detector response function-Reference-Cited by-同舟云学术

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Absolute quantification of ¹³⁷Cs activity in spent nuclear fuel with calculated detector response function

Published:2022-10-13 Issue: Volume: Page:1-9
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Sato Shunsuke¹,Nauchi Yasushi¹^ORCID,Hayakawa Takehito²,Kimura Yasuhiko³,Kashima Takao³,Futakami Kazuhiro³,Suyama Kenya³

Affiliation:

1. Central Research Institute of Electric Power Industry, Yokosuka-shi, Japan

2. National Institutes for Quantum Science and Technology, Naka-gun, Japan

3. Japan Atomic Energy Agency, Naka-gun, Japan

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00223131.2022.2130462

Reference22 articles.

1. Nuclear Fuel Cycle Facility Safety Research Committee. A guide introducing burnup credit, preliminary version. Tokai-mura (Japan): Japan Atomic Energy Research Institute; 2001, (JAERI-Tech 2001-055) [in Japanese].

2. Burnup credit in the criticality safety analyses of PWR spent fuel in transport and storage casks. Rockville (MD): United States Nuclear Regulatory Commission; 2002, (Interim Staff Guidance-8 Revision 2).

3. Regulations for the safe transport of radioactive material 2018 edition. Vienna (Austria): International Atomic Energy Agency; 2018, (IAEA Specific Safety Standards Series No. SSR-6 (Rev. 1)).

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