Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 39

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

Considerations on phenomena scaling for BEPU

Nakamura, Hideo

Proceedings of ANS International Conference on Best Estimate Plus Uncertainties Methods (BEPU 2018) (USB Flash Drive), 8 Pages, 2018/00

no abstracts in English

Journal Articles

Contributions of OECD ROSA & ROSA-2 Projects for thermal-hydraulic code validation

Nakamura, Hideo

Proceedings of Seminar on the Transfer of Competence, Knowledge and Experience gained through CSNI Activities in the Field of Thermal-Hydraulics (THICKET 2016) (CD-ROM), 29 Pages, 2016/06

no abstracts in English

Journal Articles

Development of plant dynamics analytical code named Conan-GTHTR for the Gas Turbine High Temperature Gas-cooled Reactor, 1; Code validation by Use of the experimental data of HTTR

Takamatsu, Kuniyoshi; Katanishi, Shoji; Nakagawa, Shigeaki; Kunitomi, Kazuhiko

Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(1), p.76 - 87, 2004/03

The Gas Turbine High Temperature Reactor 300 (GTHTR300) composed of an inherent safe 600MWt reactor and a closed gas turbine power conversion system is a high efficient and economically competitive HTGR to be deployed in 2010s. To analyze the plant dynamics and the thermal hydraulics of the GTHTR300, a new analytical code (Conan-GTHTR) based on 'RELAP5/MOD3' has been developed and applied to heat transfer calculations of the High Temperature Engineering Test Reactor (HTTR) for its verification. The results proved that the new code was available for transient simulations in Higt Temperature Gas-Cooled Reactor systems.

JAEA Reports

Development of analytical code 'ACCORD' for incore and plant dynamics of high temperature gas-cooled reactor

Takeda, Takeshi; Tachibana, Yukio; Kunitomi, Kazuhiko; Itakura, Hirofumi*

JAERI-Data/Code 96-032, 147 Pages, 1996/11

JAERI-Data-Code-96-032.pdf:4.58MB

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:3 Percentile:37.69(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Possibility of a pressurized water reactor concept with highly inherent heat removel following capability

Araya, Fumimasa; Murao, Yoshio

Journal of Nuclear Science and Technology, 32(4), p.339 - 350, 1995/04

 Times Cited Count:3 Percentile:37.69(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Development of REFLA/TRAC code for engineering work station

Onuki, Akira; ; Murao, Yoshio

JAERI-M 94-026, 60 Pages, 1994/03

JAERI-M-94-026.pdf:1.81MB

no abstracts in English

Journal Articles

Probabilistic accident consequence assessment codes; Second international comparison technical report

W.Nixon*; P.J.Cooper*; C.M.Bone*; S.Acharya*; U.Baeverstam*; J.Ehrhardt*; I.Hasemann*; Steinhauer, C.*; E.G.Diaz*; J.C.Glynn*; et al.

EUR-15109, 0, 338 Pages, 1994/00

no abstracts in English

Journal Articles

Feasibility study of double-flat-core type HCPWR for reactivity initiated accidents

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

Nihon Genshiryoku Gakkai-Shi, 34(8), p.776 - 786, 1992/08

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Application of subchannel code to DNB analysis of HCLWR

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

Subchannel Analysis in Nuclear Reactors, p.281 - 301, 1992/00

no abstracts in English

Journal Articles

Improvement of TRAC-PFl interfacial drag model for analysis of high-pressure horizontally-stratified two-phase flow

; Kukita, Yutaka; Anoda, Yoshinari; Nakamura, Hideo; Tasaka, Kanji

Journal of Nuclear Science and Technology, 28(1), p.33 - 44, 1991/01

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

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

JAEA Reports

DNBR analyses under steady-state and accident conditions for a double-flat-core high conversion light water reactor

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

JAERI-M 90-043, 70 Pages, 1990/03

JAERI-M-90-043.pdf:1.77MB

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

JAEA Reports

ROSA-III Experimental program for BWR LOCA/ECCS integral simulation tests

Tasaka, Kanji; Koizumi, Yasuo; Suzuki, Mitsuhiro; Anoda, Yoshinari; Kukita, Yutaka; Kumamaru, Hiroshige; Nakamura, Hideo; Yonomoto, Taisuke; Kawaji, Masahiro; Murata, Hideo

JAERI 1307, 379 Pages, 1987/11

JAERI-1307.pdf:12.18MB

no abstracts in English

Journal Articles

Post-dryout heat transfer of high-pressure steam-water two-phase flow in single rod channel and multi rod bundle

Koizumi, Yasuo; ; ; Tasaka, Kanji

Nucl.Eng.Des., 99, p.157 - 165, 1987/00

 Times Cited Count:10 Percentile:70.71(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Benchmark calculations by the nuclearcriticality safety analysis code system JACS(MGCL, KENO-IV)

Nomura, Yasushi; Katakura, Junichi; Naito, Yoshitaka; Komuro, Yuichi; Okuno, Hiroshi

JAERI 1303, 152 Pages, 1986/11

JAERI-1303.pdf:4.56MB

no abstracts in English

JAEA Reports

Implementation of reactor safety analysis code CATHARE and its use on FACOM M-380

; *; ; *

JAERI-M 86-079, 85 Pages, 1986/05

JAERI-M-86-079.pdf:1.79MB

no abstracts in English

39 (Records 1-20 displayed on this page)