Development of HT-9 for liquid-metal reactor components

Conference · Sun Jan 01 04:00:00 EST 1989 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6530612

Johnson, G D

Alloy HT-9 is being used for both duct and cladding applications in advanced liquid-metal reactor (LMR) experiments. This tempered martensitic steel was selected for use as an LMR core component material primarily because of its excellent resistance to radiation-induced swelling. Experiments conducted in the Fast Flux Test Facility (FFTF) at 410{degree}C and exposures in the range of 150 to 175 displacements per atom (dpa) have shown that Ht-9 exhibits only a 0.2 to 0.3% increase in volume. Cold-worked austenitic steels exhibit volumetric increases of 20 to 30% at 410{degree}C, Alloy HT-9 is being used for a series of fuel pin experiments in the FFTF, and these tests have achieved a burnup of 175 MWd/kg metal and a fluence of 25 {times} 10{sup 22} n/cm{sup 2} (E > 0.1 MeV) without fuel pin breach. The high confidence placed in HT-9 is based on a wide series of in- and ex-reactor experiments. Test results for these experiments are summarized in this paper.

• OSTI ID: 6530612
• Report Number(s): CONF-891103--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 60
• Country of Publication: United States
• Language: English

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42 ENGINEERING
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ALLOY-HT-9
ALLOYS
BURNUP
CHROMIUM ALLOYS
CHROMIUM STEELS
CORROSION RESISTANT ALLOYS
DUCTILE-BRITTLE TRANSITIONS
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IRRADIATION
LIQUID METAL COOLED REACTORS
MARTENSITIC STEELS
MATERIALS
MATERIALS TESTING
MOLYBDEN
MOLYBDENUM ADDITIONS
NATIONAL ORGANIZATIONS
NEUTRON FLUX
OPTIMIZATION
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PHYSICAL RADIATION EFFECTS
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REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
REACTOR SAFETY EXPERIMENTS
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RESEARCH REACTORS
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STAINLESS STEELS
STEEL-CR12MOV
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SWELLING
TEST REACTORS
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US DOE
US ORGANIZATIONS