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Published 2003 | Version v1
Conference paper Metadata-only

Behavior of uranium-zirconium-hydride fuel under reactivity initiated accident conditions

Creators

  • 1. Department of Reactor Safety Research, Japan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken 319-1195 (Japan)

Description

Pulse irradiation tests were performed with uranium-zirconium-hydride (U-ZrH1.6) fuel to examine performance under reactivity initiated accident (RIA) conditions. During the pulse irradiations U-ZrH1.6 temperature escalated up to 1240 K in pellet average. Departure from nucleate boiling (DNB) occurred in all the present tests, and cladding temperature reached 820 K at the maximum. Plastic radial deformation of the cladding was observed due to pellet-cladding mechanical interaction (PCMI). The deformation was less than 1.2% at the maximum. Rod internal pressure increase was observed during the pulse irradiation, which was probably caused by hydrogen dissociation in zirconium hydride. However, post test analyses of rod internal gas suggested that hydrogen was fully re-absorbed into zirconium in the pellet after fuel temperature decreased. Cladding ballooning or burst did not occur in the present tests. (author)

Part of:
ENS RRFM 2003. Transactions

Additional details

Publishing Information

Imprint Title
ENS RRFM 2003. Transactions
Imprint Pagination
p. 109-113
Report number
INIS-XA--652

Conference

Title
7. international topical meeting on research reactor fuel management
Dates
9-12 Mar 2003
Place
Aix-en-Provence (France)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
34073922
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CLADDING; DEFORMATION; DEPARTURE NUCLEATE BOILING; FUEL PELLETS; FUEL-CLADDING INTERACTIONS; IRRADIATION; POST-IRRADIATION EXAMINATION; REACTOR ACCIDENTS; TEMPERATURE RANGE 1000-4000 K; URANIUM COMPOUNDS; ZIRCONIUM HYDRIDES
Descriptors DEC
ACCIDENTS; ACTINIDE COMPOUNDS; BOILING; DEPOSITION; HYDRIDES; HYDROGEN COMPOUNDS; NUCLEATE BOILING; PELLETS; PHASE TRANSFORMATIONS; SURFACE COATING; TEMPERATURE RANGE; TRANSITION ELEMENT COMPOUNDS; ZIRCONIUM COMPOUNDS

Optional Information

Notes
3 refs., 8 figs., 1 tab., 1 ill.