Published 1990
| Version v1
Journal article
Fault tree for maximum credible accident probability of TR-2 research reactor
Creators
- 1. Middle East Technical Univ., Ankara (Turkey)
- 2. Atomenerjisi Komisyonu, Ankara (Turkey)
Description
In this paper, the probability of maximum credible accident at TR-2 research reactor is evaluated by using ''Fault Tree Analysis'' method. Maximum credible accident for TR-2 research reactor is considered as the simultaneous failure in both automatic and manual scram just after a loss of coolant accident. Manual scram failure is assumed to be caused by an operator error. Failure probabilities for loss of coolant accident and automatic scram failure are computed by using a computer code; TREEMASTER. Later, these probabilities are discussed, and recommendations are made
Additional details
Publishing Information
- Journal Title
- Turkish Journal of Nuclear Sciences
- Journal Volume
- 17
- Journal Issue
- 1-2
- Series
- Turk. J. Nucl. Sci.
- Journal Page Range
- 33-40
- ISSN
- 0254-5446
- CODEN
- TJNSD
INIS
- Country of Publication
- Turkey
- Country of Input or Organization
- Turkey
- INIS RN
- 23087488
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FAULT TREE ANALYSIS; MAXIMUM CREDIBLE ACCIDENT; PROBABILITY; REACTOR SHUTDOWN; SCRAM; TR-2 REACTOR
- Descriptors DEC
- ACCIDENTS; DESIGN BASIS ACCIDENTS; POOL TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SHUTDOWN; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; WATER COOLED REACTORS; WATER MODERATED REACTORS