JAEA
  • help
  • PC | SP
  • JP | EN
          
Refine your search：     
Report No.
 - 
Clear All
Search Results: Records 1-4 displayed on this page of 4
  • 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

JAEA Reports

BWR LOCA Lintegral Test Simulating a 100% Main Steam Line Break Outside Reactor Containment Vessel in ROSA-III Program, Rum 955; Analogy of Steam Line Break and Recirculation Line Small Break

; ; ; ; ; Tasaka, Kanji

JAERI-M 87-044, 151 Pages, 1987/03

JAERI-M-87-044.pdf:3.76MB

no abstracts in English

JAEA Reports

BWR 2% Main Recirculation Line Break LOCA Tests Runs 915 and 920 without HPCS in ROSA-III Program; Effects of Pressure Control System

; ; ; ; ; Koizumi, Yasuo; Tasaka, Kanji

JAERI-M 87-043, 220 Pages, 1987/03

JAERI-M-87-043.pdf:5.2MB

no abstracts in English

Journal Articles

Similarity study of ROSA-III and fist large bleak counterpart tests to BWR large bleak LOCA

; ; ; Tasaka, Kanji; J.A.Findlay*; W.A.Sutherland*

Nucl.Eng.Des., 103, p.223 - 238, 1987/00

https://doi.org/10.1016/0029-5493(87)90276-7
 Times Cited Count：1 Percentile：19.33(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

BWR Recirculation Loop Discharge Line Break LOCA Tests with Break Areas 50% and 100% Assuming HPCS Failure at ROSA-III Test Facility

; Tasaka, Kanji; ; ; ; ; ; *;

JAERI-M 85-037, 224 Pages, 1985/03

JAERI-M-85-037.pdf:5.99MB

no abstracts in English

4 (Records 1-4 displayed on this page)
  • 1