...Susan Ortner; Marcos Sanchez; John Echols; Sergio Cicero; Paul Chekhonin Using miniature compact tension (mini-C(T)) (4 mm thick, 0.16T) specimens to determine toughness in reactor pressure vessel (RPV) steels permits the ductile-to-brittle transition temperature to be derived from small amounts...

... Atomic Energy Agency to evaluate the through-wall cracking frequencies of domestic reactor pressure vessels (RPVs) considering neutron irradiation embrittlement and pressurized thermal shock (PTS) transients. In addition, efforts have been made to strengthen the applicability of PASCAL to structural...

...Kai Lu; Jinya Katsuyama; Koichi Masaki; Tadashi Watanabe; Yinsheng Li Structural integrity assessment of reactor pressure vessel (RPV) is important for the safe operation of nuclear power plant. For an RPV in a pressurized water reactor (PWR), pressurized thermal shock (PTS) resulted from rapid...

... distributions for influence parameters without over-conservativeness. To strengthen the applicability of PFM methodology in Japan, Japan Atomic Energy Agency has developed a PFM analysis code PASCAL4 which enables the failure frequency evaluation of reactor pressure vessels (RPVs) considering neutron...

...Kai Lu; Jinya Katsuyama; Yinsheng Li Structural integrity assessment of reactor pressure vessels (RPVs) is essential for the safe operation of nuclear power plants. For RPVs in pressurized water reactors (PWRs), the assessment should be performed by considering neutron irradiation embrittlement...

...Jinya Katsuyama; Kazuya Osakabe; Shumpei Uno; Yinsheng Li; Shinobu Yoshimura In Japan, to prevent nil-ductile fracture of reactor pressure vessels (RPVs) due to neutron irradiation embrittlement, deterministic fracture mechanics evaluation in accordance with the codes provided by the Japan Electric...

...Kai Lu; Jinya Katsuyama; Yinsheng Li In Japan, a probabilistic fracture mechanics (PFM) analysis code PASCAL was developed for structural integrity assessment of reactor pressure vessels (RPVs) considering neutron irradiation embrittlement and pressurized thermal shock (PTS) events. By reflecting...

... shock Q = Q -stress r = radial coordinate in the polar system R = radius of the model used in modified boundary layer formulation (mm) RPV = reactor pressure vessel R i = RPV radius (mm) SIF = stress intensity factor SLOCA = small loss-of-coolant...

.... , and Shibata , K. , 2006 , “ User's Manual and Analysis Methodology of Probabilistic Fracture Mechanics Analysis Code PASCAL ver.2 for Reactor Pressure Vessel ,” Japan Atomic Energy Agency, Report No. JAEA-Data/Code 2006-020 (in Japanese). [8] Osakabe , K. , Onizawa , K. , Shibata , K...

... of Mechanical Engineers , 2008 , “ Standard Test Method for Determination of Reference Temperature, To, for Ferritic Steels in the Transition Range ,” ASTM E1921-08. [4] International Atomic Energy Agency , 2005 , “ Application of Surveillance Programme Results to Reactor Pressure Vessel Integrity...

...), celebrated 40 years of continuous research oriented toward the safety of light-water nuclear reactor pressure vessels (RPVs). This paper presents a summary of results from those programs with a view to future activities. The HSST program was established in 1967 and initially included extensive investigations...