Embrittlement of the Shippingport reactor neutron shield tank

Conference · Mon Jan 01 04:00:00 EST 1990

OSTI ID:6969164

Chopra, O K; Shack, W J ^[1]; Rosinski, S T ^[2]

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1. Argonne National Lab., IL (USA)
2. Sandia National Labs., Albuquerque, NM (USA)

The irradiation embrittlement of the Shippingport neutron shield tank material (A212 Grade B steel) has been characterized. Irradiation increases the Charpy transition temperature (CTT) by 23--28{degree}C (41--50{degree}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 that the material is weaker in the TL orientation than LT orientation. Some effects of the location across the thickness of the wall are also observed; 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{degree}C. Although the weld metal is significantly tougher than the base metal, the shifts in CTT are comparable. The weld metal shows a strong affect of location across the thickness of the wall; only the inner regions of the weld show embrittlement. 11 refs., 14 figs., 3 tabs.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: NRC
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6969164
• Report Number(s): CONF-900789-2; ON: DE90010464
• Country of Publication: United States
• Language: English

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ALLOYS
ANNEALING
CARBON STEELS
CHARPY TEST
DESTRUCTIVE TESTING
EMBRITTLEMENT
ENRICHED URANIUM REACTORS
HEAT TREATMENTS
IMPACT TESTS
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MECHANICAL PROPERTIES
MECHANICAL TESTS
POWER REACTORS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
SHIELDING
SHIPPINGPORT REACTOR
STEEL-ASTM-A212
STEELS
STRESS ANALYSIS
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
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