Major maintenance outages in a nonpower reactor environment
The purpose of this work was to restore reliable operation of a midsize nonpower research and training reactor within the financial and manpower constraints of a university reactor facility and to establish the experience base needed to address large maintenance outages within existing resource limitations for future applications. The scenario for and the results of a major forced outage for a recurring failure in the control blade drive system are presented to demonstrate major differences in maintenance outages between power and nonpower utility versus university reactor outages. The University of Florida Training Reactor (UFTR) is a 100-kW light-water-cooled, graphite and light-water-moderated modified Argonaut-type reactor, which utilizes 93% enriched materials test reactor type of fuel. The results of this work demonstrates that a major outage of nearly 6 months' duration has restored the UFTR control blade drive system to nearly original conditions and demonstrated QA program effectiveness while maintaining a viable educational program. In addition, the experience with this outage assures that a future fuel conversion with design changes can be undertaken successfully within the unique restrictions of a nonpower reactor environment.
- Research Organization:
- Univ. of Florida, Gainesville (USA)
- OSTI ID:
- 6928547
- Report Number(s):
- CONF-8711195-; TRN: 88-028738
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 55; Conference: American Nuclear Society winter meeting, Los Angeles, CA, USA, 15 Nov 1987
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
UFTR REACTOR
REACTOR MAINTENANCE
CONTROL ELEMENTS
OUTAGES
QUALITY ASSURANCE
REACTOR CORES
REACTOR SHUTDOWN
RELIABILITY
SPECIFICATIONS
ARGONAUT TYPE REACTORS
ENRICHED URANIUM REACTORS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MAINTENANCE
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SHUTDOWNS
THERMAL REACTORS
TRAINING REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors