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Journal Articles

Uncertainty analysis of ROSA/LSTF test by RELAP5 code and PKL counterpart test concerning PWR hot leg break LOCAs

Takeda, Takeshi; Otsu, Iwao

Nuclear Engineering and Technology, 50(6), p.829 - 841, 2018/08

 Times Cited Count:6 Percentile:72.04(Nuclear Science & Technology)

Journal Articles

ROSA/LSTF test and RELAP5 analyses on PWR cold leg small-break LOCA with accident management measure and PKL counterpart test

Takeda, Takeshi; Otsu, Iwao

Nuclear Engineering and Technology, 49(5), p.928 - 940, 2017/08

 Times Cited Count:3 Percentile:40.62(Nuclear Science & Technology)

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

LSTF and BETHSY counterpart tests on PWR small break LOCA

Kumamaru, Hiroshige; G.Briday*; Kukita, Yutaka; D.Juhel*; R.Deruaz*

ANS Proc. of the 1992 National Heat Transfer Conf., p.285 - 292, 1992/00

no abstracts in English

Journal Articles

BETHSY/LSTF counterpart test on natural circulation in a pressurized water reactor

P.Bazin*; R.Deruaz*; Yonomoto, Taisuke; Kukita, Yutaka

ANS Proc. of the 1992 National Heat Transfer Conf., p.301 - 308, 1992/00

no abstracts in English

Journal Articles

Small break LOCA counter part test in the LSTF, BETHSY, LOBI and SPES test facilities

A.Annunziato*; C.Addabbo*; G.Briday*; R.Deruaz*; D.Juhel*; Kumamaru, Hiroshige; Kukita, Yutaka; C.Medich*; M.Rigamonti*

Proc. of the 5th Int. Topical Meeting on Reactor Thermal Hydraulics: NURETH-5, p.1570 - 1576, 1992/00

no abstracts in English

JAEA Reports

Comparisons of ROSA-III and FIST BWR Loss of Coolant Accident Simulation Tests

Tasaka, Kanji; ; Koizumi, Yasuo; ; ; ; ; J.A.Findlay*; W.A.Sutherland*; W.S.Hwang*; et al.

JAERI-M 85-158, 73 Pages, 1985/10

JAERI-M-85-158.pdf:1.81MB

no abstracts in English

Oral presentation

Role of IETs in reactor safety assessment

Nakamura, Hideo

no journal, , 

no abstracts in English

Oral presentation

Scaling approaches and system code as extrapolation tool

Mascari, F.*; Nakamura, Hideo; Umminger, K.*; Moon, S.-K.*; Lien, P.*; Bestion, D.*; D'Auria, F.*

no journal, , 

no abstracts in English

Oral presentation

Scaling in V&V for safety analysis

Nakamura, Hideo

no journal, , 

no abstracts in English

10 (Records 1-10 displayed on this page)
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