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Journal Articles

Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations

Kubo, Kotaro; Jang, S.*; Takata, Takashi*; Yamaguchi, Akira*

Journal of Nuclear Science and Technology, 60(4), p.359 - 373, 2023/04

 Times Cited Count:3 Percentile:82.38(Nuclear Science & Technology)

Probabilistic risk assessment (PRA) is an essential approach to improving the safety of nuclear power plants. However, this method includes certain difficulties, such as modeling of combinations of multiple hazards. Seismic-induced flooding scenario includes several core damage sequences, i.e., core damage caused by earthquake, flooding, and combination of earthquake and flooding. The flooding fragility is time-dependent as the flooding water propagates from the water source such as a tank to compartments. Therefore, dynamic PRA should be used to perform a realistic risk analysis and quantification. This study analyzed the risk of seismic-induced flooding events by coupling seismic, flooding, and thermal-hydraulics simulations, considering the dependency between multiple hazards explicitly. For requirements of safety improvement, especially in light of the Fukushima Daiichi Nuclear Power Plant accident, sensitivity analysis was performed on the seismic capacity of systems, and the effectiveness of alternative steam generator injection by a portable pump was estimated. We demonstrate the use of this simulation-based dynamic PRA methodology to evaluate the risk induced by a combination of hazards.

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:13 Percentile:80.47(Nuclear Science & Technology)

Journal Articles

In situ X-ray diffraction study of the oxide formed on alloy 600 in borated and lithiated high-temperature water

Watanabe, Masashi*; Yonezawa, Toshio*; Shobu, Takahisa; Shiro, Ayumi; Shoji, Tetsuo*

Corrosion, 72(9), p.1155 - 1169, 2016/09

 Times Cited Count:1 Percentile:6.4(Materials Science, Multidisciplinary)

Journal Articles

Conceptual designing of a reduced moderation pressurized water reactor by use of MVP and MVP-BURN

Kugo, Teruhiko

Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications, p.821 - 826, 2001/00

no abstracts in English

Journal Articles

Concept of passive safety light water reactor system (JPSR)

Murao, Yoshio; Araya, Fumimasa; Iwamura, Takamichi

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Enginering (ICONE), Vol. 2, 0, p.723 - 728, 1995/00

no abstracts in English

Journal Articles

Analysis of direct contact condensation of flowing steam onto injected water with a multifluid model of two-phase flow

; Kozawa, Yoshiyuki*; *; *

Journal of Nuclear Science and Technology, 20(12), p.1006 - 1022, 1983/00

 Times Cited Count:8 Percentile:68.41(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Semianual Progres Report on the NSRR Experiment,9

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JAERI-M 9011, 106 Pages, 1980/09

JAERI-M-9011.pdf:4.18MB

no abstracts in English

JAEA Reports

Quarterly Progress Report on the NSRR Experiments; 6 January to June 1978

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JAERI-M 7977, 150 Pages, 1978/12

JAERI-M-7977.pdf:5.48MB

no abstracts in English

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