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Zircaloy oxidation and cladding deformation in PWR-specific CORA experiments

Technical Report:

Abstract

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). [Deutsch] 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).
Authors:
Minato, K; [1]  Hering, W; [2]  Hagen, S
  1. Japan Atomic Energy Research Inst. (JAERI), Tokai-Mura (Japan)
  2. Stuttgart Univ. (Germany). Inst. fuer Kernenergetik und Energiesysteme
Publication Date:
Jul 01, 1991
Product Type:
Technical Report
Report Number:
KFK-4827
Reference Number:
SCA: 220900; 360105; 210200; PA: DEN-92:000105; SN: 92000629721
Resource Relation:
Other Information: PBD: Jul 1991
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 36 MATERIALS SCIENCE; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; FUEL CANS; OXIDATION; DEFORMATION; ZIRCALOY 4; PWR TYPE REACTORS; VERY HIGH TEMPERATURE; SIMULATION; REACTOR SAFETY EXPERIMENTS; LOSS OF COOLANT; STEAM; 220900; 360105; 210200; REACTOR SAFETY; CORROSION AND EROSION; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED
OSTI ID:
10108921
Research Organizations:
Kernforschungszentrum Karlsruhe GmbH (Germany). Hauptabteilung Ingenieurtechnik; Kernforschungszentrum Karlsruhe GmbH (Germany). Projekt Nukleare Sicherheitsforschung
Country of Origin:
Germany
Language:
English
Other Identifying Numbers:
Other: ON: DE92750150; TRN: DE9200105
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
DEN
Size:
105 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Minato, K, Hering, W, and Hagen, S. Zircaloy oxidation and cladding deformation in PWR-specific CORA experiments. Germany: N. p., 1991. Web.
Minato, K, Hering, W, & Hagen, S. Zircaloy oxidation and cladding deformation in PWR-specific CORA experiments. Germany.
Minato, K, Hering, W, and Hagen, S. 1991. "Zircaloy oxidation and cladding deformation in PWR-specific CORA experiments." Germany.
@misc{etde_10108921,
title = {Zircaloy oxidation and cladding deformation in PWR-specific CORA experiments}
author = {Minato, K, Hering, W, and Hagen, S}
abstractNote = {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). [Deutsch] 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).}
place = {Germany}
year = {1991}
month = {Jul}
}