Embrittlement of the Shippingport reactor shield tank

Conference · Sun Oct 01 04:00:00 EDT 1989

OSTI ID:5320067

Chopra, O K; Shack, W J

The irradiation embrittlement of the Shippingport neutron tank material has been characterized. Irradiation increases the Charpy transition temperature (CTT) by {approximately}25{degrees}C (45{degrees}F) and decreases the upper shelf energy. The shift in CTT is not as severe as that observed in the HFIR surveillance specimens. However, the actual value of CTT is higher than that for the HFIR data and the toughness at service temperature is low. The increase in yield stress is 51 MPa (7.4 ksi), which is comparable to the HFIR data. The results also indicate a low impact strength and higher transition temperature for the TL orientation than that for the LT orientation. Some effects of the location across the thickness of the wall are also observed for the LT specimens; CTT is slightly greater for the specimens from the inner region of the wall. 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{degrees}C. The transition curve for the annealed inner wall specimens is virtually identical to that for the as-received outer wall. The results for weld specimens from the inner and outer walls are also presented. 7 refs., 12 figs.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: NRC
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5320067
• Report Number(s): CONF-8910222-8; ON: DE90003771
• Country of Publication: United States
• Language: English

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