Refine your search:     
Report No.
 - 
Search Results: Records 1-13 displayed on this page of 13
  • 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

Journal Articles

Uncertainty analysis of toxic gas leakage accident in cogeneration high temperature gas-cooled reactor

Sato, Hiroyuki; Ohashi, Hirofumi

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 8 Pages, 2019/05

To establish a probabilistic approach for assessment of toxic gas leakage accidents in a H$$_{2}$$ plant, the present study focusses on development of an uncertainty analysis method for toxic gas concentration in a control room. The method consists of 6 steps; (1) Identification of uncertainty factors, (2) derivation of variable parameters, (3) identification of uncertainties in variable parameters, (4) identification of important factors considering the sensitivity analysis results and expert opinions, (5) uncertainty propagation analysis, (6) assessment of uncertainty analysis results. The method is then applied to representative toxic gas leakage accidents in a H$$_{2}$$ plant by IS process coupled to the HTTR. The results obtained in the study leads us to the conclusion that the suggested method can successfully characterize and quantify uncertainties in the toxic gas concentration in control room.

Journal Articles

Seismic capacity evaluation of a group of vertical U-tube heat exchanger with support frames for seismic PSA

Watanabe, Yuichi*; Muramatsu, Ken; Oikawa, Tetsukuni

Nuclear Engineering and Design, 235(23), p.2495 - 2512, 2005/12

 Times Cited Count:2 Percentile:17.57(Nuclear Science & Technology)

This paper presents an evaluation of seismic capacity of a group of vertical U-tube type heat exchangers(HXs) with support frames for residual heat removal systems of BWRs for seismic Probabilistic Safety Assessment in Japan. The median capacity was evaluated by a time history response analysis with a detailed model for a representative HX selected from four HXs. The logarithmic standard deviation(LSD) for uncertainty due to lack of knowledge was evaluated with consideration of the variabilities in three influential parameters, i.e., diameter of anchor bolt, weight of HX and position of center of gravity of HX. The dominant failure mode of HXs was the failure of anchor bolts of lugs mainly due to shearing stress. The capacity expressed in terms of zero period acceleration on the foundation of HX was evaluated to be 4,180 Gal(4.3 g) for median, LSD for uncertainty due to randomness was 0.11 from the variability in material property and LSD due to lack of knowledge was 0.21 to 0.53 depending on combination of the variability in design parameters to be considered.

Journal Articles

Insights from the seismic PSA of the BWR model plant at JAERI

; Kondo, Masaaki; Watanabe, Yuichi*; *; *; Muramatsu, Ken

Proc. of Int. Topical Meeting on Probabilistic Safety Assessment (PSA'99), 1, p.77 - 84, 1999/00

no abstracts in English

Journal Articles

Development of systems reliability analysis code SECOM-2 for seismic PSA

; Kondo, Masaaki; *; Watanabe, Yuichi*; *; Muramatsu, Ken

Reliab. Eng. Syst. Saf., 62(3), p.251 - 271, 1998/00

 Times Cited Count:11 Percentile:51.13(Engineering, Industrial)

no abstracts in English

Journal Articles

Development of a computational framework of uncertainty analysis for level 2 PSA to consider both aleatory and epistemic uncertainties

Muramatsu, Ken; *; *

20th CNS Nuclear Simulation Symposium, p.1 - 10, 1997/00

no abstracts in English

Journal Articles

Utilization of PSA with consideration of its limitations

Abe, Kiyoharu; Muramatsu, Ken

Transactions of the 13th Int. Conf. on Structural Mechanics in Reactor Technology (SMiRT),Vol. 4, 0, p.647 - 652, 1995/00

no abstracts in English

Journal Articles

Uncertainties remaining in severe accident phenomena and related research activities at JAERI

Abe, Kiyoharu; Sugimoto, Jun; *

Reliab. Eng. Syst. Saf., 45, p.3 - 17, 1994/00

 Times Cited Count:1 Percentile:25.75(Engineering, Industrial)

no abstracts in English

Journal Articles

Analysis of uncertainty factors on source terms for severe accidents

*; Muramatsu, Ken

Dai-6-Kai Kakuritsuronteki Anzen Hyoka (PSA) Ni Kansuru Kokunai Shimpojiumu Rombunshu (IAE-9206), p.25 - 33, 1993/01

no abstracts in English

JAEA Reports

BASIC programs for calculation of sensitivities and uncertainties of fission product decay heat

Iijima, Shungo*; Katakura, Junichi

JAERI-M 90-197, 87 Pages, 1990/11

JAERI-M-90-197.pdf:2.34MB

no abstracts in English

JAEA Reports

Users manual of VARS; A Computer code system for uncertainty analysis

Ishigami, Tsutomu; Kobayashi, Kensuke; *; *; *

JAERI-M 88-082, 72 Pages, 1988/05

JAERI-M-88-082.pdf:1.49MB

no abstracts in English

Oral presentation

Uncertainty evaluation of seismic response for a nuclear facility

Choi, B.; Nishida, Akemi; Takada, Tsuyoshi*

no journal, , 

In this paper, in order to clarify the influence of difference due to modeling methods on the results of seismic response analysis for a nuclear facility, seismic response analysis using various earthquake events was conducted and the findings obtained from the uncertainty assessment of the response result due to the difference in modeling methods are reported.

Oral presentation

Evaluation of effect of difference building modelings on seismic response of nuclear facilities

Choi, B.; Nishida, Akemi; Muramatsu, Ken*; Takada, Tsuyoshi*

no journal, , 

no abstracts in English

13 (Records 1-13 displayed on this page)
  • 1