User's manual and analysis methodology of probabilistic fracture mechanics analysis code PASCAL-SP Ver. 2 for piping (Contract research)

Yamaguchi, Yoshihito; Mano, Akihiro; Katsuyama, Jinya; Masaki, Koichi*; Miyamoto, Yuhei*; Li, Y.

JAEA-Data/Code 2020-021, 176 Pages, 2021/02

JAEA-Data-Code-2020-021.pdf:5.26MB

In Japan Atomic Energy Agency, as a part of researches on the structural integrity assessment and seismic safety assessment of aged components in nuclear power plants, a probabilistic fracture mechanics (PFM) analysis code PASCAL-SP (PFM Analysis of Structural Components in Aging LWR - Stress Corrosion Cracking at Welded Joints of Piping) has been developed to evaluate failure probability of piping. The initial version was released in 2010, and after that, the evaluation targets have been expanded and analysis functions have been improved based on the state-of-the art technology. Now, it is released as Ver. 2.0. In the latest version, primary water stress corrosion cracking in the environment of Pressurized Water Reactor, nickel based alloy stress corrosion cracking in the environment of Boiling Water Reactor, and thermal embrittlement can be taken into account as target age-related degradation. Also, many analysis functions have been improved such as incorporations of the latest stress intensity factor solutions and uncertainty evaluation model of weld residual stress. Moreover, seismic fragility evaluation function has been developed by introducing evaluation methods including crack growth analysis model considering excessive cyclic loading due to large earthquake. Furthermore, confidence level evaluation function has been incorporated by considering the epistemic and aleatory uncertainties related to influence parameters in the probabilistic evaluation. This report provides the user's manual and analysis methodology of PASCAL-SP Ver. 2.0.

Probabilistic fracture mechanics analyses of nuclear pressure vessels under PTS events

Yagawa, Genki*; Yoshimura, Shinobu*; *; Hirano, Masashi

Nucl. Eng. Des., 174(1), p.91 - 100, 1997/00

https://doi.org/10.1016/S0029-5493(97)00072-1

no abstracts in English

Methodology for estimationg realistic responses of buildings and components under earthquake motion and its application

; *; *; *; Abe, Kiyoharu

JAERI-Research 96-059, 73 Pages, 1996/11

JAERI-Research-96-059.pdf:2.72MB

no abstracts in English

Development of seismic PSA methodology at JAERI

Muramatsu, Ken; ; Matsumoto, Kiyoshi; ; Kondo, Masaaki; *

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering, Vol. 3, 0, p.1333 - 1340, 1995/00

no abstracts in English

Probabilistic evaluation of seismic isolation effect with respect to siting of a fusion reactor facility

Takeda, M.*; Okawa, Yoshinao; Akutsu, Yoichi; Suzuki, Hideyuki; *; *

Nihon Kenchiku Gakkai Taikai Gakujutsu Koen Kogaishu, 0, p.45 - 46, 1994/09

no abstracts in English