Fault tree analysis of a research reactor
Description
Fault Tree Analysis Techniques have been used to assess the safety system of the ZED-2 Research Reactor at the Chalk River Nuclear Laboratories. This turned out to be a strong test of the techniques involved. The resulting fault tree was large and because of inter-links in the system structure the tree was not modularized. In addition, comprehensive documentation was required. After a brief overview of the reactor and the analysis, this paper concentrates on the computer tools that made the job work. Two types of tools were needed; text editing and forms management capability for large volumes of component and system data, and the fault tree codes themselves. The solutions (and failures) are discussed along with the tools we are already developing for the next analysis
Availability note (English)
MF available from INIS under the Report Number.Files
20064180.pdf
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Additional details
Additional titles
- Subtitle (English)
- Computer tools that work
Publishing Information
- Imprint Pagination
- 15 p.
- Report number
- AECL--9202
Conference
- Title
- Canadian conference on industrial computer systems.
- Dates
- 28-30 May 1986.
- Place
- Montreal, PQ (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 20064180
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DATA PROCESSING; FAULT TREE ANALYSIS; PROBABILISTIC ESTIMATION; REACTOR CONTROL SYSTEMS; RISK ASSESSMENT; ZED-2 REACTOR
- Descriptors DEC
- AIR COOLED REACTORS; CONTROL SYSTEMS; GAS COOLED REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; NATURAL URANIUM REACTORS; ORGANIC COOLED REACTORS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TANK TYPE REACTORS; THERMAL REACTORS