A new code for predicting the thermo-mechanical and irradiation behavior of metallic fuels in sodium fast reactors-Reference-Cited by-同舟云学术

A new code for predicting the thermo-mechanical and irradiation behavior of metallic fuels in sodium fast reactors

Published:2010-01 Issue:2-3 Volume:396 Page:283-293
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Karahan Aydın,Buongiorno Jacopo

Publisher

Elsevier BV

Subject

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

Reference42 articles.

1. US DOE Nuclear Energy Research Advisory Committee and The Generation IV International Forum, A Technology Roadmap for Generation IV Nuclear Energy Systems, US Department of Energy, Report, December 2002.

2. US Department of Energy, Global Nuclear Energy Partnership Strategic Plan, US Department of Energy, Report No. GNEP-167312, Rev. 0, 2007.

3. Metallic fast reactor fuels

4. Swelling behavior of U-Pu-Zr fuel

5. On the failure of fast reactor fuel pins

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