'CAWP' as CAE system for structural design
- 1. Mitsubishi Heavy Industries Ltd., Tokyo (Japan)
Description
A CAE system called ''CAWP'' was developed for purposes of rationalization and quality improvement of structural design in nuclear power plant. CAWP system works through stress analysis including FEM modeling, FEM calculation, structural evaluation and reporting, and consists of 5 fully interconnected subsystem modules. They are the preprocess graphic module for modeling, check and run module for calculation, postprocess module for evaluation, postprocess graphic module, and stock and control module for data processing. By this computerization, costs and periods of time which are needed for stress analysis are reduced. Furthermore, the quality assurance of stress analysis is sustained by cautious procedures to keep the analytical data of this system consistent and traceable. (author)
Additional details
Publishing Information
- Journal Title
- Mitsubishi Juko Giho
- Journal Volume
- 23
- Journal Issue
- 6
- Series
- Mitsubishi Juko Giho.
- Journal Page Range
- 711-716
- ISSN
- 0387-2432
- CODEN
- MIJGA
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 18077008
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BUILDING MATERIALS; CREEP; DATA PROCESSING; EFFICIENCY; F CODES; MONJU REACTOR; QUALITY ASSURANCE; STRESS ANALYSIS; USES
- Descriptors DEC
- BREEDER REACTORS; COMPUTER CODES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS