Abstract
As a part of the aging and structural integrity research for LWR components, a new PFM (Probabilistic Fracture Mechanics) code PASCAL (PFM Analysis of Structural Components in Aging LWR) has been developed since FY1996. This code evaluates the failure probability of an aged reactor pressure vessel subjected to transient loading such as PTS (Pressurized Thermal Shock). The development of the code has been aimed to improve the accuracy and reliability of analysis by introducing new analysis methodologies and algorithms considering the recent development in the fracture mechanics methodologies and computer performance. The code has some new functions in optimized sampling and cell dividing procedure in stratified Monte Carlo simulation, elastic-plastic fracture criterion of R6 method, extension analysis models in semi-elliptical crack, evaluation of effect of thermal annealing and etc. In addition, an input data generator of temperature and stress distribution time histories was also prepared in the code. Functions and performance of the code have been confirmed based on the verification analyses and some case studies on the influence parameters. The present phase of the development will be completed in FY2000. Thus this report provides the user's manual and theoretical background of the code. (author)
Shibata, Katsuyuki;
Onizawa, Kunio;
[1]
Li, Yinsheng;
Kato, Daisuke
[2]
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
- Fuji Research Institute Corporation, Tokyo (Japan)
Citation Formats
Shibata, Katsuyuki, Onizawa, Kunio, Li, Yinsheng, and Kato, Daisuke.
Development of probabilistic fracture mechanics code PASCAL and user's manual.
Japan: N. p.,
2001.
Web.
Shibata, Katsuyuki, Onizawa, Kunio, Li, Yinsheng, & Kato, Daisuke.
Development of probabilistic fracture mechanics code PASCAL and user's manual.
Japan.
Shibata, Katsuyuki, Onizawa, Kunio, Li, Yinsheng, and Kato, Daisuke.
2001.
"Development of probabilistic fracture mechanics code PASCAL and user's manual."
Japan.
@misc{etde_20188326,
title = {Development of probabilistic fracture mechanics code PASCAL and user's manual}
author = {Shibata, Katsuyuki, Onizawa, Kunio, Li, Yinsheng, and Kato, Daisuke}
abstractNote = {As a part of the aging and structural integrity research for LWR components, a new PFM (Probabilistic Fracture Mechanics) code PASCAL (PFM Analysis of Structural Components in Aging LWR) has been developed since FY1996. This code evaluates the failure probability of an aged reactor pressure vessel subjected to transient loading such as PTS (Pressurized Thermal Shock). The development of the code has been aimed to improve the accuracy and reliability of analysis by introducing new analysis methodologies and algorithms considering the recent development in the fracture mechanics methodologies and computer performance. The code has some new functions in optimized sampling and cell dividing procedure in stratified Monte Carlo simulation, elastic-plastic fracture criterion of R6 method, extension analysis models in semi-elliptical crack, evaluation of effect of thermal annealing and etc. In addition, an input data generator of temperature and stress distribution time histories was also prepared in the code. Functions and performance of the code have been confirmed based on the verification analyses and some case studies on the influence parameters. The present phase of the development will be completed in FY2000. Thus this report provides the user's manual and theoretical background of the code. (author)}
place = {Japan}
year = {2001}
month = {Mar}
}
title = {Development of probabilistic fracture mechanics code PASCAL and user's manual}
author = {Shibata, Katsuyuki, Onizawa, Kunio, Li, Yinsheng, and Kato, Daisuke}
abstractNote = {As a part of the aging and structural integrity research for LWR components, a new PFM (Probabilistic Fracture Mechanics) code PASCAL (PFM Analysis of Structural Components in Aging LWR) has been developed since FY1996. This code evaluates the failure probability of an aged reactor pressure vessel subjected to transient loading such as PTS (Pressurized Thermal Shock). The development of the code has been aimed to improve the accuracy and reliability of analysis by introducing new analysis methodologies and algorithms considering the recent development in the fracture mechanics methodologies and computer performance. The code has some new functions in optimized sampling and cell dividing procedure in stratified Monte Carlo simulation, elastic-plastic fracture criterion of R6 method, extension analysis models in semi-elliptical crack, evaluation of effect of thermal annealing and etc. In addition, an input data generator of temperature and stress distribution time histories was also prepared in the code. Functions and performance of the code have been confirmed based on the verification analyses and some case studies on the influence parameters. The present phase of the development will be completed in FY2000. Thus this report provides the user's manual and theoretical background of the code. (author)}
place = {Japan}
year = {2001}
month = {Mar}
}