Refine your search:     
Report No.
 - 
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

Fuel temperature analysis method for channel-blockage accident in HTTR

Maruyama, So; Fujimoto, Nozomu; Sudo, Yukio; Kiso, Yoshihiro*; *

Nucl. Eng. Des., 150, p.69 - 80, 1994/00

 Times Cited Count:5 Percentile:47.66(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Verification of in-core thermal and hydraulic analysis code FLOWNET/TRUMP for the High Temperature Engineering Test Reactor(HTTR) at JAERI

Maruyama, So; Sudo, Yukio; Saito, Shinzo; Kiso, Yoshihiro*; *

Proc. of the 4th Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Vol. 1, p.227 - 232, 1989/12

no abstracts in English

JAEA Reports

Verification of combined thermal-hydraulic and heat conduction analysis code FLOWNET/TRUMP

Maruyama, So; Fujimoto, Nozomu; Kiso, Yoshihiro*; Murakami, Tomoyuki*; Sudo, Yukio

JAERI-M 88-173, 76 Pages, 1988/09

JAERI-M-88-173.pdf:1.78MB

no abstracts in English

JAEA Reports

Disign and evaluation of core flow distribution in High Temperature Engineering Test Reactor(HTTR)

Maruyama, So; Fujimoto, Nozomu; Kiso, Yoshihiro*; Murakami, Tomoyuki*; Takikawa, Noboru*; *; Sudo, Yukio

JAERI-M 88-154, 147 Pages, 1988/08

JAERI-M-88-154.pdf:2.9MB

no abstracts in English

JAEA Reports

Verification of in-vessel thermal and hydraulic analysis code "FLOWNET"

Maruyama, So; Murakami, Tomoyuki*; Kiso, Yoshihiro*; Sudo, Yukio

JAERI-M 88-138, 39 Pages, 1988/07

JAERI-M-88-138.pdf:1.03MB

no abstracts in English

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