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Reduced Enrichment for Research and Test Reactors
Nuclear Science and Engineering Division at Argonne
U.S. Department of Energy

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Abstracts and Available Papers Presented at the
2002 International RERTR Meeting

SAFETY ASPECTS ON DEPENABILITY MANAGEMENT FOR A TRIGA RESEARCH REACTOR IN ROMANIA

Gheorghe VIERU, PhD, IAEA Technical Expert

Institute for Nuclear Research, Pitesti, Romania

ABSTRACT

Safety on the management for a nuclear research reactor involves a "good dependability* management" of the activities, such as: reliability, availability, maintainability and maintenance support. In order to evaluate the safety management aspects intended to be applied at a research reactor management, the performance dependability indicators and their impact over the availability and reactor safety have to be established. The document ISO 9000-4/IEC 300 –1 “Dependability Management” (1995), describes five internationally agreed indicators of the reactor equipment dependability, each of them can be used for corrective maintenance or for preventive maintenance, such as: I1 - equipment Maintenance Frequency; I2 - equipment Maintenance Effort; I3- equipment Maintenance Downtime Factor; I4 - equipment Maintenance Contribution to the System Function Downtime Factor; I5 - equipment Maintenance Contribution to the reactor Capability Loss Factor. The paper presents an evaluation of those 5 mentioned indicators with referring only at the primary circuit of the INR's TRIGA research reactor and conclusion. The analyzed period was stated between 1994-1999. It is to be noted that this type of analyze is performed for the first time for a research reactor.


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Contact:
Dr. Gheorghe Vieru

Head, Reliability and Testing Laboratory
Institute for Nuclear Research, Pitesti
P.O. Box 78, Jud. Arges
0300 Pitesti, Romania
Phone: (40 248) 213400 ext. 130
Fax: (40 248) 262449
E-mail: [email protected]

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Last modified on July 29, 2008 11:33 +0200