Thermal-Neutron capture cross-section measurements of Neptunium-237 with graphite thermal column in KUR-Reference-Cited by-同舟云学术

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Thermal-Neutron capture cross-section measurements of Neptunium-237 with graphite thermal column in KUR

Published:2022-04-11 Issue:11 Volume:59 Page:1388-1398
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

Nakamura Shoji¹,Shibahara Yuji²,Endo Shunsuke¹,Kimura Atsushi¹

Affiliation:

1. Nuclear Data Center, Nuclear Science and Engineering Center, Japan Atomic Energy Agency, Naka-gun, Japan

2. Radioactive Waste Management, Division of Nuclear Engineering Science, Institute for Integrated Radiation and Nuclear Science, Kyoto University, Sennan-gun, Japan

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00223131.2022.2058639

Reference39 articles.

1. Nuclear fuel cycle strategies including Partitioning and Transmutation

2. Radioactive waste partitioning and transmutation within advanced fuel cycles: Achievements and challenges

3. Evaluation of the burnout efficiency of Np-237 and Am-241 in a BN-600 reactor with a modified core

4. Minor actinide transmutation characteristics in AP1000

Cited by 1 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Measurements of neutron capture cross-sections for nuclides of interest in decommissioning: ⁴⁵ Sc, ⁶³ Cu, ⁶⁴ Zn, ¹⁰⁹ Ag, and ¹¹³ In;Journal of Nuclear Science and Technology;2024-05-07

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