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.

R&D on mercury target for spallation neutron source to improve the durability under high power operation, 5; Application of anomaly detection and diagnosis for structural integrity evaluation of a mercury target vessel

Saruta, Koichi; Murata, Atsushi*; Maeno, Koki*; Wakui, Takashi; Naoe, Takashi; Kogawa, Hiroyuki; Li, Y.*; Teshigawara, Makoto; Haga, Katsuhiro; Futakawa, Masatoshi

no journal, , 

In the spallation neutron source at the J-PARC, the mercury target vessel incorporates several countermeasures against cavitation erosion, which reduces the vessel's lifetime. Anomaly detection and diagnosis of the vessel will play an increasingly important role in long-term operation under increased proton beam powers. A laser Doppler vibrometer and a microphone are employed in an attempt to evaluate the correlation of anomalies with the vibration and sound that are excited on the vessel by the incident proton beams, generated by the mercury flow running through the double-wall structure, and caused by the microbubble generator. An overview of the development plan of anomaly detection and diagnosis for the target vessel using vibration and sound measurement is presented and discussed based on preliminary results obtained in water-loop experiments.