User's manual and analysis methodology of probabilistic fracture mechanics analysis code PASCAL Ver.2 for reactor pressure vessel (Contract research)
Creators
- 1. Japan Atomic Energy Agency, Nuclear Safety Research Center, Tokai, Ibaraki (Japan)
- 2. Mizuho Information and Research Inst., Tokyo (Japan)
Description
As a part of the aging structural integrity research for LWR components, the probabilistic fracture mechanics (PFM) analysis code PASCAL (PFM Analysis of Structural Components in Aging LWR) has been developed in JAEA. This code evaluates the conditional probabilities of crack initiation and fracture of a reactor pressure vessel (RPV) under transient conditions such as pressurized thermal shock (PTS). 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 and computer performance. PASCAL Ver.1 has functions of optimized sampling in the stratified Monte Carlo simulation, elastic-plastic fracture criterion of the R6 method, crack growth analysis models for a semi-elliptical crack, recovery of fracture toughness due to thermal annealing and so on. Since then, under the contract between the Ministry of Economy, Trading and Industry of Japan and JAEA, we have continued to develop and introduce new functions into PASCAL Ver.2 such as the evaluation method for an embedded crack, KI database for a semi-elliptical crack considering stress discontinuity at the base/cladding interface, PTS transient database, and others. A generalized analysis method is proposed on the basis of the development of PASCAL Ver.2 and results of sensitivity analyses. Graphical user interface (GUI) including a generalized method as default values has been also developed for PASCAL Ver.2. This report provides the user's manual and theoretical background of PASCAL Ver.2. (author)
Availability note (English)
Available from JAEA; DOI: https://doi.org/10.11484/jaea-data-code-2006-020
Files
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Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 379 p.
- Report number
- JAEA-Data/Code--2006-020
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 38021266
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AGING; CRACK PROPAGATION; EMBRITTLEMENT; FRACTURE MECHANICS; FRACTURE PROPERTIES; IRRADIATION; MANUALS; NUMERICAL ANALYSIS; P CODES; PRESSURIZATION; PROBABILISTIC ESTIMATION; REACTOR VESSELS; THERMAL SHOCK; TRANSIENTS
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; CONTAINERS; DOCUMENT TYPES; MATHEMATICS; MECHANICAL PROPERTIES; MECHANICS
Optional Information
- Notes
- 47 refs., 134 figs., 28 tabs.