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Journal Articles

ROSA/LSTF tests and RELAP5 posttest analyses for PWR safety system using steam generator secondary-side depressurization against effects of release of nitrogen gas dissolved in accumulator water

Takeda, Takeshi; Onuki, Akira*; Kanamori, Daisuke*; Otsu, Iwao

Science and Technology of Nuclear Installations, 2016, p.7481793_1 - 7481793_15, 2016/00

AA2016-0048.pdf:5.15MB

 Times Cited Count:2 Percentile:16.06(Nuclear Science & Technology)

Journal Articles

Burnup importance function and its application to OECD/NEA/BUC phase II-A and II-C models

Okuno, Hiroshi; Tonoike, Kotaro; Sakai, Tomohiro*

Proceedings of International Conference on the New Frontiers of Nuclear Technology; Reactor Physics, Safety and High-Performance Computing (PHYSOR 2002) (CD-ROM), 8 Pages, 2002/10

As the burnup proceeds, reactivity of fuel assemblies for light water reactors decreases by depletion of fissile nuclides, especially in the axially central region. In order to describe the importance of the end regions to the reactivity change, a burnup importance function was introduced as a weighting function to a local burnup variation contributed to a reactivity decrease. The function was applied to the OECD/NEA/BUC Phase II-A model and a simplified Phase II-C model. The application to Phase II-A model clearly showed that burnup importance of the end regions increases as burnup and/or cooling time increases. Comparison of the burnup importance function for different initial enrichments was examined. The application result to the simplified Phase II-C model showed that the burnup importance function was helpful to find the most reactive fuel burnup distribution under the conditions that the average fuel burnup was kept constant and the variations in the fuel burnup were within the maximum and minimum measured values.

Journal Articles

Evaluation of multiple steam generator tube rupture event

Seul, K. W.*; Yonomoto, Taisuke; Bang, Y. S.*; Anoda, Yoshinari

Proceedings of 6th Biennial Conference on Engineering Systems Design and Analysis (ESDA2002), 9 Pages, 2002/07

no abstracts in English

Journal Articles

Thermal-hydraulic research on future reactor systems in the ROSA program at JAERI

Yonomoto, Taisuke; Otsu, Iwao; Svetlov, S.*

Proceedings of 3rd Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-3), p.521 - 528, 2002/00

A research project is being conducted at the Japan Atomic Energy Research Institute on thermal hydraulics for the future reactor systems. The present paper provides the belief description of the project, followed by two recent topics: the natural circulation in the PWR loop and the condensation heat transfer for a passive cooling system. For the first topic, we discuss the importance of the modeling of the nonuniform flow behavior among SG U-tubes for the assessment of the long-term decay heat removal systems relying on the SG secondary side cooling. Such a system is planned to be used in APWR+, a Japanese next-generation PWR. The condensation heat transfer was investigated using the data obtained at the SPOT test facility in Russia. The results have shown that the measured heat transfer rates on the inner surface of the tube consisting of several bends and short straight sections can be predicted using the existing correlations with the accuracy of several percentage, although the correlations are based typically on the data taken using relatively long straight tube.

Journal Articles

Design of advanced integral-type marine reactor, MRX

Kusunoki, Tsuyoshi; Odano, Naoteru; Yoritsune, Tsutomu; Ishida, Toshihisa; Hoshi, Tsutao*; Sako, Kiyoshi*

Nuclear Engineering and Design, 201(2-3), p.155 - 175, 2000/10

 Times Cited Count:56 Percentile:93.58(Nuclear Science & Technology)

no abstracts in English

Journal Articles

ROSA/LSTF experiments on low-pressure natural circulation heat removal for next-generation PWRs

Yonomoto, Taisuke; Otsu, Iwao

Proceedings of 12th Pacific Basin Nuclear Conference (PBNC 2000), Vol.1, p.317 - 329, 2000/00

no abstracts in English

Journal Articles

Safety analysis of a submersible compact reactor SCR for under-sea research vessel

Yoritsune, Tsutomu; Kusunoki, Tsuyoshi; Odano, Naoteru; Ishida, Toshihisa

Proceedings of the 4th JSME-KSME Thermal Engineering Conference, p.1_31 - 1_36, 2000/00

no abstracts in English

Journal Articles

Secondary-side depressurization during PWR cold-leg small break LOCAs based on ROSA-V/LSTF experiments and analyses

Asaka, Hideaki; Anoda, Yoshinari; Kukita, Yutaka*;

Journal of Nuclear Science and Technology, 35(12), p.905 - 915, 1998/12

 Times Cited Count:16 Percentile:75.23(Nuclear Science & Technology)

no abstracts in English

Journal Articles

A Method to calculate sensitivity coefficients of reactivity to errors in estimating amounts of nuclides found in irradiated fuel

; Suyama, Kenya;

Journal of Nuclear Science and Technology, 35(3), p.240 - 242, 1998/03

 Times Cited Count:1 Percentile:15.05(Nuclear Science & Technology)

no abstracts in English

Journal Articles

RELAP5/MOD3 code analyses of LSTF experiments on intentional primary-side depressurization following sblocas with totally failed HPI

; Kukita, Yutaka*; Asaka, Hideaki; M.Wang*; Otani, Etsuo*

Nuclear Technology, 126(3), p.331 - 339, 1998/00

 Times Cited Count:9 Percentile:55.86(Nuclear Science & Technology)

no abstracts in English

Journal Articles

International studies on burnup credit criticality safety by an OECD/NEA working Group

M.C.Brady*; ; M.D.DeHart*; A.Nouri*; E.Sartori*

Proc. of Int. Conf. on the Phys. of Nucl. Sci. and Technol., 1, p.624 - 630, 1998/00

no abstracts in English

Journal Articles

PWR small break Loss-of-Coolant-Accident Experiment at ROSA-V/LSTF with a combination of secondary-side depressurization and gravity-driven safety injection

Yonomoto, Taisuke; ; Kukita, Yutaka

Journal of Nuclear Science and Technology, 34(6), p.571 - 581, 1997/06

 Times Cited Count:5 Percentile:41.84(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Status of transient thermal-hydraulic demonstration test program at JAERI

Iguchi, Tadashi; Onuki, Akira; Iwaki, Chikako*; Kureta, Masatoshi; Akimoto, Hajime

Proc. of 5th Int. Conf. on Nuclear Engineering (ICONE-5), p.1 - 9, 1997/00

no abstracts in English

Journal Articles

Application of simplified condensation model to PWR LBLOCA transient analysis with TRAC-PF1 code

; Murao, Yoshio

Journal of Nuclear Science and Technology, 33(4), p.290 - 297, 1996/04

 Times Cited Count:3 Percentile:31.96(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Application of PSA methodology to design improvement of JAERI passive safety reactor (JPSR)

Iwamura, Takamichi; Araya, Fumimasa; Murao, Yoshio

Journal of Nuclear Science and Technology, 33(4), p.316 - 326, 1996/04

 Times Cited Count:1 Percentile:14.04(Nuclear Science & Technology)

no abstracts in English

Journal Articles

ROSA/AP600 testing; Facility modifications and initial test results

Kukita, Yutaka; Yonomoto, Taisuke; ; Nakamura, Hideo; Kumamaru, Hiroshige; Anoda, Yoshinari; T.J.Boucher*; M.G.Ortiz*; R.A.Shaw*; R.R.Schultz*

Journal of Nuclear Science and Technology, 33(3), p.259 - 265, 1996/03

 Times Cited Count:34 Percentile:90.94(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Multiphase flow technology in development of light water reactors

Konsoryu, 10(4), p.360 - 363, 1996/00

no abstracts in English

Journal Articles

NRC Confirmatory AP600 safety system phase I testing in the ROSA/AP600 test facility

G.S.Rhee*; Kukita, Yutaka; R.R.Schultz*

NUREG/CP-0149 (Vol. 1), 0, p.243 - 264, 1996/00

no abstracts in English

Journal Articles

Findings of an international study on burnup credit

M.C.Brady*; ; M.D.DeHart*; Okuno, Hiroshi; A.Nouri*; E.Sartori*

PHYSOR 96: Int. Conf. on the Physics of Reactors, 4, p.L41 - L52, 1996/00

no abstracts in English

Journal Articles

Safety features of JAERI passive safety reactor (JPSR)

Murao, Yoshio

Proc. of 11th KAIF/KNS Annual Conf., 0, p.587 - 596, 1996/00

no abstracts in English

127 (Records 1-20 displayed on this page)