Refine your search:     
Report No.
 - 
Search Results: Records 1-7 displayed on this page of 7
  • 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

Steady-state and transient DNB analyses for JAERI passive safety reactor (JPSR) using COBRA-IV-I and RETRAN-02/Mod3 codes

Okubo, Tsutomu; X.Jiang*; Araya, Fumimasa; Ochiai, Masaaki

JAERI-Research 98-042, 49 Pages, 1998/08

JAERI-Research-98-042.pdf:1.58MB

no abstracts in English

Journal Articles

Transient analysis for design of primary coolant pump adopted to JAERI passive safety reactor JPSR

Araya, Fumimasa; Murao, Yoshio; Iwamura, Takamichi

Journal of Nuclear Science and Technology, 32(10), p.1039 - 1046, 1995/10

 Times Cited Count:5 Percentile:49.5(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Experimental study on DNB heat flux of plate-type fuel in pressurized condition

; ; Kaminaga, Masanori; Ishitsuka, Etsuo; ; Sudo, Yukio; Saito, Minoru;

JAERI-M 92-097, 61 Pages, 1992/07

JAERI-M-92-097.pdf:2.42MB

no abstracts in English

Journal Articles

Evaluation of DNBR under operational and accident conditions for double-flat-core type HCLWR

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

Journal of Nuclear Science and Technology, 28(1), p.45 - 58, 1991/01

no abstracts in English

Journal Articles

Thermal hydraulic feasibility study of a double-flat-core type High Conversion Light Water Reactor

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

Thermal Hydraulics of Advanced Nuclear Reactors, p.31 - 38, 1990/00

no abstracts in English

Journal Articles

Analytical study on thermal-hydraulic behavior of transient from forced circulation to natural circulation in JRR-3

Hirano, Masashi; Sudo, Yukio

Journal of Nuclear Science and Technology, 23(4), p.352 - 368, 1986/00

 Times Cited Count:18 Percentile:84.84(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Thermal-hydraulic conceptual design of the new multipurpose research reactor succeeding to JRR-3

Arai, Masaji; Tsumura, Takashi

no journal, , 

The new multipurpose research reactor is a 30 MW thermal power, swimming pool type research reactor and will be constructed instead of JRR-3 for utilization of the neutron beam, irradiation, training and so on. The core thermal-hydraulic conceptual design of the new multipurpose reactor was performed for the forced convection cooling modes. The key criteria are first to avoid the nucleate boiling anywhere in the core and second to have enough safety margin to departure from nucleate boiling for normal operation conditions. As the results of the thermal-hydraulic analysis, the optimum coolant velocity in the standard fuel element and the core inlet pressure were obtained.

7 (Records 1-7 displayed on this page)
  • 1