Refine your search:     
Report No.
 - 
Search Results: Records 1-11 displayed on this page of 11
  • 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

A Steady-state simulation model of gas separation system by hollow-filament type membrane module

Iwai, Yasunori; Yamanishi, Toshihiko; Nishi, Masataka

Journal of Nuclear Science and Technology, 36(1), p.95 - 104, 1999/01

 Times Cited Count:12 Percentile:66.16(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Numerical evaluation of interfacial area concentration using the immiscible lattice gas

Watanabe, Tadashi; Ebihara, Kenishi

Nucl. Eng. Des., 188(1), p.111 - 121, 1999/00

 Times Cited Count:6 Percentile:44.07(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Benchmark calculation of subchannel analysis codes

JAERI-Data/Code 96-004, 109 Pages, 1996/02

JAERI-Data-Code-96-004.pdf:2.3MB

no abstracts in English

Journal Articles

Study of premixing phase of steam explosion with JASMINE code in ALPHA program

Moriyama, Kiyofumi; Yamano, N.; Maruyama, Yu; Kudo, Tamotsu; Sugimoto, Jun

Proc. of ASME$$cdot$$JSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 1(PART B), p.903 - 915, 1996/00

no abstracts in English

Journal Articles

Thermal-hydraulic characteristics of coolant in the core bottom structure of the High-Temperature Engineering Test Reactor

Inagaki, Yoshiyuki; Kunitomi, Kazuhiko; ; Ioka, Ikuo*;

Nuclear Technology, 99, p.90 - 103, 1992/07

 Times Cited Count:9 Percentile:64.20(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Estimation of hot streak in core bottom structure of high temperature gas-cooled reactor; Thermal mixing test of coolant in core bottom structure of HENDEL

Inagaki, Yoshiyuki; Suzuki, Kunihiro; Ioka, Ikuo*; Kunitomi, Kazuhiko;

Nihon Kikai Gakkai Rombunshu, B, 57(542), p.3520 - 3525, 1991/10

no abstracts in English

JAEA Reports

JAEA Reports

Critical heat flux experiments for high conversion light water reactor, 3; Heated length: 0.5$$sim$$1.0m, P/D: 1.126$$sim$$1.2, number of rods: 4$$sim$$7

Iwamura, Takamichi; Okubo, Tsutomu; ; ; Murao, Yoshio

JAERI-M 90-044, 158 Pages, 1990/03

JAERI-M-90-044.pdf:2.81MB

no abstracts in English

Journal Articles

Thermal mixing test of coolant in the core bottom structure of a High Temperature Engineering Test Reactor

Inagaki, Yoshiyuki; Kunugi, Tomoaki;

Nucl. Eng. Des., 123, p.77 - 86, 1990/00

 Times Cited Count:9 Percentile:66.43(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Effect of two-phase mixing coefficient on subchannel analysis and CHF prediction

Iwamura, Takamichi; Okubo, Tsutomu; ; ; Murao, Yoshio

JAERI-M 89-127, 47 Pages, 1989/09

JAERI-M-89-127.pdf:1.18MB

no abstracts in English

Journal Articles

Performance test of the upper head injection system at the ROSA-II test facility

Tasaka, Kanji; ; ; Soda, Kunihisa; ; ;

Nuclear Technology, 45(2), p.121 - 139, 1979/00

 Times Cited Count:0

no abstracts in English

11 (Records 1-11 displayed on this page)
  • 1