Performance of ZrC-coated particle fuel in irradiation and postirradiationheating tests

Journal Article · Sun Nov 01 00:00:00 EST 1992 · Journal of the American Ceramic Society; (United States)

DOI:https://doi.org/10.1111/j.1151-2916.1992.tb04375.x· OSTI ID:7140041

Ogawa, T; Fukuda, K; Kashimura, S; Tobita, T; Kobayashi, F; Kado, S; Miyanishi, H; Takahashi, I; Kikuchi, T ^[1]

---

1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

This paper reports on the ZrC-coated UO[sub 2] particle which is a promising fuel for high-temperature gas-cooled reactors. Particle fuels with multiple layers of pyrolytic carbon and ZrC have been irradiation-tested to a maximum fast-neutron fluence exceeding 2 [times] 10[sup 25]/m[sup 2] (E [gt] 29 fJ). In-reactor fission-gas release measured at a burnup of 1.5 at.% was minimal. The failure fraction by postirradiation examination was null for all samples. The ZrC-coated particles at 4 at.% burnup were postirradiation heated to 2400[degrees]C/min without failure until after 6000 s at the maximum temperature. It was found that the ZrC layer could sustain a large strain at such high temperatures. The behavior is in strong contrast with that of SiC of standard Triso coating, which is brittle to very high temperatures.

• OSTI ID: 7140041
• Journal Information: Journal of the American Ceramic Society; (United States), Vol. 75:11; ISSN 0002-7820
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
FUEL ELEMENTS
POST-IRRADIATION EXAMINATION
HTGR TYPE REACTORS
REACTOR COMPONENTS
MATERIALS TESTING
URANIUM DIOXIDE
SURFACE COATING
ZIRCONIUM CARBIDES
COATINGS
FAST NEUTRONS
HEAT RESISTANT MATERIALS
IRRADIATION
NEUTRON FLUENCE
TEMPERATURE RANGE 1000-4000 K
ACTINIDE COMPOUNDS
BARYONS
CARBIDES
CARBON COMPOUNDS
CHALCOGENIDES
DEPOSITION
ELEMENTARY PARTICLES
FERMIONS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HADRONS
MATERIALS
NEUTRONS
NUCLEONS
OXIDES
OXYGEN COMPOUNDS
REACTORS
TEMPERATURE RANGE
TESTING
TRANSITION ELEMENT COMPOUNDS
URANIUM COMPOUNDS
URANIUM OXIDES
ZIRCONIUM COMPOUNDS
360206* - Ceramics
Cermets
& Refractories- Radiation Effects
210300 - Power Reactors
Nonbreeding
Graphite Moderated
220300 - Nuclear Reactor Technology- Fuel Elements
050700 - Nuclear Fuels- Fuels Production & Properties