Report of the advanced neutron source (ANS) aluminum cladding corrosion workshop

Conference · Wed Feb 01 00:00:00 EST 1989

OSTI ID:5688149

Hanson, G H; Gibson, G W; Griess, J C; Pawel, R E; Pace, N E; Ryskamp, J M ^[1]

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1. EG and G Idaho, Inc., Idaho Falls, ID (USA)

The Advanced Neutron Source (ANS) Corrosion Workshop on aluminum cladding corrosion in reactor environments is summarized. The Workshop was held to examine the aluminum cladding oxidation studies being conducted in support of the ANS design. This report was written principally to provide a record of the ideas and judgments expressed by the workshop attendees. The ANS operating heat flux is significantly higher than that in existing reactors, and early experiments indicate that there may be an aluminum cladding oxidation problem unique to higher heat fluxes or associated cladding temperatures that, if not solved, may limit the operation of the ANS to unacceptably low power levels. A brief description of the information presented by each speaker is included along with a compilation of the most significant ideas and recommended research areas. The appendixes contain a copy of the workshop agenda and a list of attendees.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5688149
• Report Number(s): CONF-8811203-; ON: DE90001281; TRN: 89-029379
• Resource Relation: Conference: American Nuclear Society (ANS) aluminium cladding corrosion workshop, Idaho Falls, ID (USA), 16-17 Nov 1988
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
ALUMINIUM
CORROSION
FUEL CANS
ALUMINIUM OXIDES
ATR REACTOR
CORROSION PRODUCTS
ETR REACTOR
FUEL-CLADDING INTERACTIONS
NEUTRON FLUX
OXIDATION
SOLUBILITY
THICKNESS
URANIUM
ACTINIDES
ALUMINIUM COMPOUNDS
CHALCOGENIDES
CHEMICAL REACTIONS
DIMENSIONS
ELEMENTS
ENRICHED URANIUM REACTORS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MATERIALS TESTING REACTORS
METALS
OXIDES
OXYGEN COMPOUNDS
RADIATION FLUX
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
220300 - Nuclear Reactor Technology- Fuel Elements
360106 - Metals & Alloys- Radiation Effects