Lv11
48 积分 2025-09-12 加入
Development of Probabilistic Fracture Mechanics Analysis Code for Chinese Reactor Pressure Vessel: PET‐CR
1个月前
已完结
Sensitivity Study on the Effects of Nondestructive Examinations on Failure Probabilities of Reactor Pressure Vessels
3个月前
已完结
Improvements on Evaluation Functions of a Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessels
3个月前
已完结
Confidence Interval Comparisons For Probability of Detection On Hit/Miss Data
3个月前
已关闭
Probabilistic Fracture Mechanics Codes for Piping International Benchmark—Part 2: Probabilistic Comparisons
1年前
已完结
Probabilistic Fracture Mechanics Codes for Piping International Benchmark – Part 1: Deterministic Comparisons
1年前
已完结
Corrosion fatigue crack growth behavior of alloy 52 M in high-temperature water
1年前
已关闭
Behavior mechanism and prediction models of stress corrosion cracking of stainless steels in pressurized water reactors
1年前
已完结
Technical Basis for Code Case N-809 on Reference Fatigue Crack Growth Curves for Austenitic Stainless Steels in Pressurized Water Reactor Environments
1年前
已完结
Technical Basis for Revision of Code Case N-809 on Reference Fatigue Crack Growth Curves for Austenitic Stainless Steels in Pressurized Water Reactor Environments
1年前
已完结
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