Data and analyses for Inconel X750 springs irradiated in SURV-1, -3, -4, -5, and -6
In 1965, eight surveillance subassemblies were placed in row 12 of EBR-II, where the irradiation temperature would be near the sodium-inlet temperature of 371/sup 0/C. At the same time, two other surveillance subassemblies were placed in the primary-tank storage basket, which receives minimal neutron exposure but is immersed in primary sodium and experiences a temperature of 371/sup 0/C. Each subassembly contained 18 preloaded springs made of Inconel X750. Springs from four of the in-core subassemblies and from one subassembly in the storage basket have been evaluated to determine rates of irradiation-enhanced deformation at neutron exposures of up to 4.2 dpa. The creep coefficient derived from the stress-relaxation measurements on the springs was 1.0 x 10/sup -12/ (Pa . dpa)/sup -1/ for neutron exposures of 4.2 dpa (3751 days) at an in-reactor temperature of 371/sup 0/C. The relaxation behavior was adequately described by a creep equation that was linear in neutron fluence and applied stress. Springs encapsulated in helium showed in-reactor relaxation rates identical to those of springs exposed to the flowing primary sodium. The creep coefficient derived from this work in Inconel X750 springs was almost the same as the creep coefficients determined for various austenitic stainless steel alloys.
- Research Organization:
- Argonne National Lab., Ill. (USA)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6834298
- Report Number(s):
- ANL-77-11
- Country of Publication:
- United States
- Language:
- English
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