Development of an integrity evaluation system on the basis of cooperative virtual reality environment for reactor pressure vessel
- 1. SAFE Research Center, Sungkyunkwan Univ., Kyunggi-do (Korea, Republic of)
- 2. Korea Inst. of Nuclear Safety, Daijon (Korea, Republic of)
- 3. Inst. of Environmental Studies, The Univ. of Tokyo, Tokyo (Japan)
Description
Since early 1950's, the fracture mechanics has brought significant impact on structural integrity assessment in a wide range of industries such as power, transportation, civil and petrochemical industries, especially in nuclear power plant industries. For the last two decades, significant efforts have been devoted in developing defect assessment procedures, and as a result, various fitness-for-purpose or fitness-for-service codes have been developed. From another aspect, recent advances in IT (information technologies) bring rapid changes in various engineering fields. IT enables people to share information through network and thus provides concurrent working environment without limitations of locations. For this reason, a network system based on internet or intranet bas been appeared in various fields of business. Evaluating the integrity of critical components is one of the most critical issues in the nuclear industry. In order to evaluate the integrity of structures, a complicated and collaborative procedure is required including periodical in-service inspection, fracture mechanics analysis, etc. And thus, experts in different fields have to cooperate to resolve the integrity problem. In this paper, an integrity evaluation system on the basis of cooperative virtual reality environment for reactor pressure vessel which adopts IT into a structural integrity evaluation procedure for reactor pressure vessel is introduced. The proposed system uses virtual reality (VR) technique, virtual network computing (VNC) and knowledge based programs. This system is able to support 3-dimensional virtual reality environment and provide experts to co-operate each other by accessing related data through internet. The proposed system is expected to provide a more efficient integrity evaluation for reactor pressure vessel. (orig.)
Additional details
Publishing Information
- Journal Title
- Key Engineering Materials
- Journal Volume
- 270-273
- Journal Issue
- pt.3
- Series
- Advances in nondestructive evaluation
- Journal Page Range
- p. 2244-2249
- ISSN
- 1013-9826
- CODEN
- KEMAEY
Conference
- Title
- 11. Asia-Pacific conference on non-destructive testing
- Acronym
- APCNDT-11
- Dates
- 3-7 Nov 2003
- Place
- Jeju Island (Korea, Republic of)
INIS
- Country of Publication
- Switzerland
- Country of Input or Organization
- Switzerland
- INIS RN
- 35104384
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CALCULATIONS; COMPUTER CODES; DISTRIBUTED DATA PROCESSING; FRACTURE MECHANICS; INFORMATION SYSTEMS; MECHANICAL STRUCTURES; NUCLEAR POWER PLANTS; PRESSURE VESSELS; THREE-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- CONTAINERS; DATA PROCESSING; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; PROCESSING; THERMAL POWER PLANTS