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Journal Articles

Failure probability evaluation for steam generator tubes with wall-thinning

Yamaguchi, Yoshihito; Mano, Akihiro; Li, Y.

Transactions of the 27th International Conference on Structural Mechanics in Reactor Technology (SMiRT 27) (Internet), 10 Pages, 2024/03

The steam generator (SG) is an important component of a pressurized water reactor. In addition, local wall-thinning has been reported in SG tubes. The burst differential pressure, considering both the internal and external pressures from the primary and secondary coolant systems, should be predicted for the failure probability evaluation or structural integrity assessment of SG tubes. In this study, based on the results of burst tests performed in Japan and the United States, we improved the existing burst pressure estimation method for SG tubes with wall-thinning. In addition, as an example of the utilization of the improved burst pressure estimation method, the conditional failure probabilities for SG tubes with local wall-thinning, which is necessary for probabilistic risk assessment and risk-informed decision making, are calculated considering the dimensions of the wall-thinning.

Journal Articles

Development of probabilistic analysis code for evaluating seismic fragility of aged pipes with wall-thinning

Yamaguchi, Yoshihito; Nishida, Akemi; Li, Y.

Proceedings of ASME 2022 Pressure Vessels and Piping Conference (PVP 2022) (Internet), 7 Pages, 2022/07

The wall-thinning is one of the most important age-related degradation phenomena in nuclear piping systems. Furthermore, in recent years, several nuclear power plants in Japan have experienced severe earthquakes. Therefore, failure probability analysis and fragility evaluation of piping systems, taking both wall-thinning and seismic response stresses into consideration, have become increasingly important in seismic probabilistic risk assessment. In Japan Atomic Energy Agency, in order to evaluate the failure probability of aged piping system with wall-thinning, a probabilistic analysis code PASCAL-EC was developed. In this study, to evaluate the seismic fragility of a wall-thinned pipe, a model of seismic response stress considering the wall-thinning effect, a failure evaluation method for wall-thinned pipes, and functions related to uncertainties treatment for important influence parameters have been introduced to PASCAL-EC. In this paper, the improved PASCAL-EC is outlined and preliminary results of the seismic fragility evaluation performed using this code are provided.

Journal Articles

Evaluation of clearance level of uranium and TRU waste

Kanno, Mitsuhiro*; Takeda, Seiji; Minase, Naofumi; Kato, Hideo; Kimura, Hideo

JAERI-Conf 2004-011, p.131 - 132, 2004/07

no abstracts in English

Journal Articles

Probabilistic safety assessment for HLW disposal system

Takeda, Seiji; Minase, Naofumi; Kimura, Hideo

JAERI-Conf 2004-011, p.133 - 134, 2004/07

no abstracts in English

Journal Articles

Research of uncertainty on long-term safety assessment for radioactive waste disposal

Takeda, Seiji; Kimura, Hideo

JAERI-Conf 2003-018, p.111 - 112, 2003/10

no abstracts in English

Journal Articles

Derivation methods on the clearance levels for nuclear reactors

Okoshi, Minoru

Hoken Butsuri, 34(4), p.353 - 358, 1999/12

no abstracts in English

JAEA Reports

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