Article ID Journal Published Year Pages File Type
1569128 Journal of Nuclear Materials 2007 15 Pages PDF
Abstract

Ni-base alloys were considered for the Prometheus space reactor pressure vessel with operational parameters of ∼900 K for 15 years and fluences up to 1.6 × 1020 n/m2 (E > 0.1 MeV). This paper reviews the effects of irradiation on the behavior of Ni-base alloys and shows that radiation-induced swelling and creep are minor considerations compared to significant embrittlement with neutron exposure. While the mechanism responsible for radiation-induced embrittlement is not fully understood, it is likely a combination of helium embrittlement and solute segregation that can be highly dependent on the alloy composition and exposure conditions. Transmutation calculations show that detrimental helium levels would be expected at the end of life for the inner safety rod vessel (thimble) and possibly the outer pressure vessel, primarily from high energy (E > 1 MeV) n, α reactions with 58Ni. Helium from 10B is significant only for the outer vessel due to the proximity of the outer vessel to the BeO control elements. Recommendations for further assessments of the material behavior and methods to minimize the effects of radiation damage through alloy design are provided.

Related Topics
Physical Sciences and Engineering Energy Nuclear Energy and Engineering
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