JAEA
  • help
  • PC | SP
  • JP | EN
          
Refine your search：     
Report No.
 - 
Clear All
Search Results: Records 1-5 displayed on this page of 5
  • 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

Development of computer code PRECIP-II for calculation of Zr-steam reaction; Comparison of calculation with experiments in temperature transient

;

Journal of Nuclear Science and Technology, 17(4), p.291 - 300, 1980/00

https://doi.org/10.3327/jnst.17.291
 Times Cited Count：6 Percentile：58.20(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Oxidation of zircaloy-4 under high temperature steam atmosphere and its effect on ductility of cladding

; ;

Journal of Nuclear Science and Technology, 15(8), p.589 - 596, 1978/08

https://doi.org/10.3327/jnst.15.589
 Times Cited Count：61

no abstracts in English

JAEA Reports

Zircaloy-Steam Reaction and Embrittlement of the Oxidized Zircaloy Tube Under Postulated Loss-of-Coolant-Accident Conditions; Zircaloy-Steam Reaction Above 1200$$^{circ}$$C

; ;

JAERI-M 6879, 23 Pages, 1977/01

JAERI-M-6879.pdf:1.28MB

no abstracts in English

JAEA Reports

Zircaloy-System Reaction and Related Embrittlement for Zircaloy Cladding under a Simulated Loss-of Coolant Accident

; ; ;

JAERI-M 6601, 26 Pages, 1976/06

JAERI-M-6601.pdf:1.75MB

no abstracts in English

Journal Articles

High temperature oxydation of hastelloy X in high velocity, impurified helium

Yamamoto, Katsumune; ;

Nihon Genshiryoku Gakkai-Shi, 17(11), p.609 - 616, 1975/11

https://doi.org/10.3327/jaesj.17.609

no abstracts in English

5 (Records 1-5 displayed on this page)
  • 1