Application of fuzzy set theory for safety culture and safety management assessment of Kartini research reactor
Creators
- 1. Yogyakarta Nuclear Research Centre, Yogyakarta (Indonesia)
- 2. Department of Plant Design and Safety, Otto-Von-Guericke-University, Magdeburg (Germany)
Description
The safety culture status of nuclear power plant is usually assessed through interview and/or discussions with personnel and management in plant, and an assessment of the pertinent documentation. The approach for safety culture assessment described in IAEA Safety Series, make uses of a questionnaire composed of questions which require 'Yes' or 'No' as an answer. Hence, it is basically a check-list approach which is quite common for safety assessments in industry. Such a procedure ignores the fact that the expert answering the question usually has knowledge which goes far beyond a mere binary answer. Additionally, many situations cannot readily be described in such restricted terms. Therefore, it was developed a checklist consisting of questions which are formulated such that they require more than a simple 'yes' or 'no' as an answer. This allows one to exploit the expert knowledge of the analyst appropriately by asking him to qualify the degree of compliance of each of the topics examined. The method presented has proved useful in assessing the safety culture and quality of safety management of the research reactor. The safety culture status and the quality of safety management of Kartini research reactor is rated as 'average'. The method is also flexible and allows one to add questions to existing areas or to introduce new areas covering related topics
Files
31043069.pdf
Files
(744.7 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:7263a3019b640e7d347124df47e6670f
|
744.7 kB | Preview Download |
System files
(12.8 kB)
| Name | Size | Download all |
|---|
Additional details
Publishing Information
- Imprint Title
- Research reactor utilization, safety and management. Proceedings
- Imprint Pagination
- [CD-ROM]
- Journal Issue
- no. 4/C
- Series
- C and S papers series
- Journal Page Range
- [6 p.]
- ISSN
- 1562-4153
Conference
- Title
- International symposium on research reactor utilization, safety and management
- Dates
- 6-10 Sep 1999
- Place
- Lisbon (Portugal)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 31043069
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUZZY LOGIC; IAEA; KARTINI-PPNY REACTOR; REACTOR SAFETY; RECOMMENDATIONS; RISK ASSESSMENT; SAFETY ANALYSIS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; INTERNATIONAL ORGANIZATIONS; MATHEMATICAL LOGIC; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SOLID HOMOGENEOUS REACTORS; TRIGA TYPE REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- IAEA-SM--360/32P
- Notes
- Data in PDF format; Acrobat Reader for Windows 3.x, 95, 98, NT, MacIntosh and UNIX included; 9 refs, 2 figs, 4 tabs
- Secondary number(s)
- IAEA-CSP--4/C; IAEA-SM--360