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Steady-state tritium inventory in plasma-facing tungsten for fusion reactors: An effective calculation method and implications of calculation results

  • Published:2023-04 Issue: Volume:577 Page:154294
  • ISSN:0022-3115
  • Container-title:Journal of Nuclear Materials
  • language:en
  • Short-container-title:Journal of Nuclear Materials

Author:

Oda TakujiORCID

Funder

National Research Foundation of Korea

National Supercomputing Center, Korea Institute of Science and Technology Information

Ministry of Science, ICT and Future Planning

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference83 articles.

1. Physics basis for the first ITER tungsten divertor;Pitts;Nucl. Mater. Energy.,2019

2. Design concept of K-DEMO for near-term implementation;Kim;Nucl. Fusion.,2015

3. Japan's efforts to develop the concept of JA DEMO during the past decade;Tobita;Fusion Sci. Technol.,2019

4. Tritium inventory in ITER plasma-facing materials and tritium removal procedures;Roth;Plasma Phys. Control. Fusion,2008

5. First result of deuterium retention in neutron-irradiated tungsten exposed to high flux plasma in TPE;Shimada;J. Nucl. Mater.,2011
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