Experimental study on thermal stratification in a reactor vessel of innovative sodium-cooled fast reactor: mitigation approach of temperature gradient across stratification interface
Bibliographic Information
- Other Title
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- Experimental study on thermal stratification in a reactor vessel of innovative sodium cooled fast reactor mitigation approach of temperature gradient across stratification interface
- Special issue on NTHAS6
- Special issue on NTHAS6
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Journal
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- Journal of nuclear science and technology = 日本原子力学会英文論文誌
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Journal of nuclear science and technology = 日本原子力学会英文論文誌 47 (9), 829-838, 2010-09
Tokyo : Atomic Energy Society of Japan
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Keywords
Details 詳細情報について
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- CRID
- 1520853833130819968
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- NII Article ID
- 10026648634
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- NII Book ID
- AA00703720
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- ISSN
- 00223131
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- NDL BIB ID
- 10796392
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- Text Lang
- en
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- NDL Source Classification
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- ZM35(科学技術--物理学)
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- Data Source
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- NDL
- CiNii Articles
