Published 1996
| Version v1
Book
Nuclear fuel rod qualification by ramp testing and pre- and post irradiation examination
Description
As imposed by the safety requirements, fuel rods for Power Reactors have to demonstrate their ability to withstand power variations without failure. Smooth power variations, such as those due to load following, as well as severe power transients, such as those due to unexpected reactivity excursions, have to be taken into consideration. In the BR-2 reactor, power ramps can be performed on a single rod up to high ratings with a high accuracy on the power. Pre- and post-irradiation examinations are performed in the hot laboratories of the SCK-CEN. Both facilities are briefly described and results concerning the behaviour of fuel rods when ramped are given
Additional details
Publishing Information
- Publisher
- World Scientific Publishing Co. Pte. Ltd.
- Imprint Place
- Singapore (Singapore)
- Imprint Title
- Research Facilities for the Future of Nuclear Energy
- Imprint Pagination
- 557 p.
- Journal Page Range
- p. 187-194
Conference
- Title
- Research Facilities for the Future of Nuclear Energy
- Dates
- 4-6 Jun 1996
- Place
- Brussels (Belgium)
INIS
- Country of Publication
- Singapore
- Country of Input or Organization
- Belgium
- INIS RN
- 29038197
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BELGIUM; BR-02 REACTOR; FUEL ELEMENT FAILURE; HOT LABS; POST-IRRADIATION EXAMINATION
- Descriptors DEC
- BERYLLIUM MODERATED REACTORS; DEVELOPED COUNTRIES; ENRICHED URANIUM REACTORS; EUROPE; LABORATORIES; METAL MODERATED REACTORS; NUCLEAR FACILITIES; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE