Published July 1991 | Version v1
Report Restricted

Zircaloy oxidation and cladding deformation in PWR-specific CORA experiments

Creators

  • 1. Japan Atomic Energy Research Inst. (JAERI), Tokai-Mura (Japan)
  • 2. Stuttgart Univ. (Germany). Inst. fuer Kernenergetik und Energiesysteme

Description

Out-of-pile bundle experiments (zircaloy 4) are performed in the CORA facility to investigate the behavior of PWR fuel elements during severe fuel damage (SFD) accidents. Within the international cooperation the most significant phenomena such as cladding deformation, oxidation (especially the zirconium/steam reaction), melt formation, melt release, and relocation which were found in all tests have been analyzed. (orig./MM)

Availability note (English)

MF available from INIS under the Report Number.

Abstract (German)

Am Kernforschungszentrum Karlsruhe werden in der Buendeltestanlage CORA Out-of-pile Experimente zur Untersuchung des Verhaltens von DWR-Brennelementen unter Bedingungen, wie sie bei schweren Kernschaeden (Severe fuel damage, SFD) auftreten koennen, durchgefuehrt. Im Rahmen der internationalen Kooperation wurde der Einfluss der wichtigsten Phaenomene wie z.B. der Huellrohrdeformation, der Huellrohroxidation (Zirkon-Wasser-Reaktion), der Schmelzebildung, -freisetzung und -verlagerung auf den weiteren Schadensablauf im Buendel untersucht. (orig./MM)

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Additional details

Publishing Information

Imprint Pagination
105 p.
Report number
KFK--4827

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
23015030
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Descriptors DEI
ALLOY-ZR98SN-4; DEFORMATION; FUEL CANS; LOSS OF COOLANT; OXIDATION; PWR TYPE REACTORS; REACTOR SAFETY EXPERIMENTS; SIMULATION; STEAM; TEMPERATURE RANGE 1000-4000 K
Descriptors DEC
ACCIDENTS; ALLOYS; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; HEAT RESISTING ALLOYS; IRON ADDITIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; TEMPERATURE RANGE; THERMAL REACTORS; TIN ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS