Đang chuẩn bị liên kết để tải về tài liệu:
Probabilistic analysis of PWR Reactor Pressure Vessel under Pressurized Thermal Shock

Đang chuẩn bị nút TẢI XUỐNG, xin hãy chờ

This paper describes the benchmark study for deterministic and probabilistic fracture mechanics analyzing the beltline region under PTS by using FAVOR code developed by Oak Ridge National Laboratory. The Monte Carlo method was employed in FAVOR code to calculate the conditional probability of crack initiation. | Probabilistic analysis of PWR Reactor Pressure Vessel under Pressurized Thermal Shock

TÀI LIỆU LIÊN QUAN

Báo cáo khoa học: "Improving Probabilistic Latent Semantic Analysis with Principal Component Analysis"

A whitening approach to probabilistic canonical correlation analysis for omics data integration

Báo cáo khoa học: "A PROBABILISTIC APPROACH TO GRAMMATICAL ANALYSIS OF WRITTEN ENGLISH BY COMPUTER"

Lecture Engineering economy - Chapter 12: Probabilistic risk analysis

Probabilistic pushover analysis of reinforced concrete frame structures using dropout neural network

Research " A COST EFFECTIVENESS AND PROBABILISTIC SENSITIVITY ANALYSIS OF OPPORTUNISTIC SCREENING VERSUS SYSTEMATIC SCREENING FOR SIGHT THREATENING DIABETIC EYE DISEASE "

Perception and neural function in probabilistic models of the brain: Part 1

Discrete Wavelet transform technique and probabilistic neural network application in recognition of power capacitor switchings

Occurrence and probabilistic health risk assessment (PRA) of dissolved metals in surface water sources in Southern Peru

Probabilistic analysis of PWR Reactor Pressure Vessel under Pressurized Thermal Shock