JAEA
  • help
  • PC | SP
  • JP | EN
          
Refine your search：     
Report No.
 - 
Clear All
Search Results: Records 1-2 displayed on this page of 2
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Thermal and stress analysis of a fusion reactor first wall with non-circular coolant channels

Seki, Masahiro; ; ; *; *

Computational Mechanics 86;Theory and Applications, p.8 - 97, 1986/00

no abstracts in English

Oral presentation

Development of analysis methods for assessing the structural integrity of reactor pressure vessel

Katsuyama, Jinya; Uno, Shumpei; Li, Y.

no journal, , 

no abstracts in English

2 (Records 1-2 displayed on this page)
  • 1