Irradiation embrittlement of the shippingport neutron shield tank

Conference · Tue Aug 01 04:00:00 EDT 1989

OSTI ID:5498418

Chopra, O K; Shack, W J

The irradiation embrittlement of the Shippingport neutron shield tank material has been characterized. The results indicate embrittlement of the A212 grade B steel from low-temperature, low-flux environment. However, the shifts in Charpy transition temperature are lower than those for the HFIR surveillance samples. The data agree well with results from high flux test reactors. Annealing studies indicate complete recovery of embrittlement after a 2-h anneal at 400{degree}C. 10 refs., 12 figs., 1 tab.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: NRC
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5498418
• Report Number(s): CONF-8910274-2; ON: DE90001942
• Country of Publication: United States
• Language: English

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CARBON STEELS
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MECHANICAL TESTS
NEUTRON FLUENCE
POWER REACTORS
PWR TYPE REACTORS
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RESEARCH AND TEST REACTORS
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SHIELDING MATERIALS
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