Development of a PFM code for evaluating reliability of pressure components subject to transient loading

Nuclear Engineering and Design

Volumn 208, Issue 1, 2001, Pages 1-13

  Shibata, Katsuyuki ^a   Kato, Daisuke ^b   Li, Yinsheng ^b  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

^b Fuji Research Institute Corporation   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

COMPUTER SIMULATION; CRACK PROPAGATION; MATHEMATICAL MODELS; MONTE CARLO METHODS; NUCLEAR ENERGY; TRANSIENTS;

TRANSIENT LOADING;

PRESSURE VESSEL CODES;

EID: 0035845332     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(01)00361-2     Document Type: Article

References (16)

1. Sensitivity analysis of failure probability on PTS benchmark problem of pressure vessel using a probabilistic fracture mechanics analysis code
2. Further experimental verification of warm prestress effect under pressurized thermal shock (PTS)
3. Progress of LWR structural safety research at JAERI
4. Development of PFM Code for Evaluating Reliability of Pressure Components Subjected to Transient Loading
5. Recent progress on irradiation embrittlement and related reliability studies on pressure vessel steels
6. Format and content of plant specific pressurized thermal shock safety analysis reports for pressurized water reactor
7. Format and content of report for thermal annealing of reactor pressure vessels