Utilization of the Halden reactor for supporting development of fuel with enhanced accident tolerance

Conference · Fri Jul 01 04:00:00 EDT 2016

OSTI ID:22750086

McGrath, M. A.; Bennett, P.; Thoresen, H. ^[1]

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1. Institute for Energy Technology, OECD Halden Reactor Project, Halden (Norway)

This paper gives an overview of the facilities and capabilities of the Halden Boiling Water Reactor (HBWR) for supporting the development and validation of nuclear fuels. The pressurized water loops, the auxiliary in-reactor experimental systems, the instrumented test fuel assemblies and the post-irradiation facilities are succinctly described. The HBWR is contributing to the validation of new fuel types proposed as candidates for enhanced accident tolerance fuel (EATF) concepts, including uranium nitride compounds and microcell UO{sub 2}. Another point is the validation of new cladding materials for EATF. A new experiment is to be carried out to study the corrosion and irradiation creep and growth behaviour of several candidate claddings compared against a reference of Zircaloy-4. The candidate claddings include coated and surface modified Zr-based alloys, optimized FeCrAl and a Mo-based cladding.

• Research Organization: American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22750086
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CLADDING
FUEL ASSEMBLIES
HBWR REACTOR
IRRADIATION PLANTS
NUCLEAR FUELS
URANIUM DIOXIDE
URANIUM NITRIDES
VALIDATION
ZIRCALOY 4