Published January 1980
| Version v1
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Power ramp experiments in the nuclear power plant Biblis-A
- 1. Kraftwerk Union A.G., Erlangen (Germany, F.R.)
- 2. Rheinisch-Westfaelisches Elektrizitaetswerk A.G., Essen (Germany, F.R.)
Description
Two ramp experiments have been performed in the Biblis-A reactor on two-cycle standard fuel assemblies. The power range of these experiments covered the conditions representative for extreme transient operation of large PWRs. In order to perform such ramp tests in power reactors, a modified control rod inserted into the assembly for its second operational cycle was rapidly withdrawn. Furthermore, ramp powers of up to 410 W/cm have been achieved only by special reactor operation deviating from standard operation. The fuel rods with burnups of up to 30,600 MWd/t(M) showed a very good ramping behaviour. No fuel defects have occurred. This has been demonstrated on a statistically significant number of fuel rods. (author)
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Additional details
Publishing Information
- Imprint Title
- Specialists' meeting on power ramping and power cycling of water reactor fuel and its significance to fuel behaviour, Arles, France, 14-18 May 1979
- Journal Page Range
- p. 45-50.
- Report number
- IWGFPT--5
Conference
- Title
- Specialists' meeting on power ramping and power cycling of water reactor fuel and its significance to fuel behaviour.
- Dates
- 14 - 18 May 1979.
- Place
- Arles, France.
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 12632894
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BIBLIS REACTOR; FISSION PRODUCT RELEASE; FUEL ELEMENT FAILURE; FUEL RODS; FUEL-CLADDING INTERACTIONS; PERFORMANCE; REACTOR OPERATION
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; OPERATION; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS