Evaluation of the tightness of fuel elements in pressurized water reactors during operation and fuel element exchange (in German)
Book
·
OSTI ID:4325078
From international nuclear industries fair; Basel, Switzerland (16 Oct 1972). Based on the operating experience gained at the Beznau Nuclear Power Plant, criteria are established and discussed which would allow the operator to evaluate the performance of the fuel in reference to fuel leakage during operation. Furthermore a method offering the possibility to approximately locate defective fuel elements during operation is given. Finally a review of the fuel element sipping methods used up to now during refueling is presented and a new method developed and tested at the Beznau Plant including the sipping results obtained is described. (auth)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-29-026010
- OSTI ID:
- 4325078
- Country of Publication:
- Country unknown/Code not available
- Language:
- German
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