Published June 2000 | Version v1
Computer medium Open

Application of fuzzy set theory for safety culture and safety management assessment of Kartini research reactor

  • 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

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Part of:
Research reactor utilization, safety and management. Proceedings

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