Experiment design for the neutron irradiation of PM-HIP alloys for nuclear reactors

• Published in: Nuclear engineering and design 2023-02, Vol.402, p.112114, Article 112114
• Main Authors: Guillen, Donna Post, Wharry, Janelle P., Housley, Gregory K., Hale, Cody D., Brookman, Jason V., Gandy, David W.
• Format: Article
• Language: English
• Subjects: Neutron irradiation; Neutronics; Ni-base alloy; Powder metallurgy; Stainless steel; Thermal analysis
• ISSN: 0029-5493; 1872-759X
• DOI: 10.1016/j.nucengdes.2022.112114

•Experiment design for neutron irradiation of PM-HIP alloys in the Advanced Test Reactor.•Test train assemblies house sealed drop-in capsules containing specimens.•PM-HIP and wrought/cast specimens fabricated from six nuclear structural alloys.•Specimens configured as disks, compact tension specimens and tensile bars.•Thermal, structural and neutronic analyses conducted to support design objectives. This article describes the design of an Advanced Test Reactor (ATR) drop-in neutron irradiation experiment aiming to directly compare the performance of nuclear structural alloys fabricated by powder metallurgy with hot isostatic pressing (PM-HIP) against conventional casting or forging. There is growing interest in PM-HIP alloys for nuclear applications because of their microstructural uniformity, superior mechanical properties, and reduced dependence on welding and machining, compared to cast/forged alloys. Nuclear code-qualification of PM-HIP alloys requires neutron irradiation testing to demonstrate performance under relevant conditions. In this experiment, six nuclear structural alloys were irradiated: Ni-based alloys 625 and 690, Grade 91 ferritic steel, SA508 pressure vessel steel, and 304L and 316L austenitic stainless steels. The experiment is assembled into seven capsules in four test trains and irradiated in three ATR inboard A positions. Both the PM-HIP and cast/forged versions of each alloy were irradiated under nearly identical conditions for comparative purposes, to target doses of 1 ± 0.2 and 3 ± 0.2 dpa at temperatures of 300 ± 50 °C and 400 ± 50 °C. A thorough description of the experiment design and thermal, structural and neutronic analyses performed to ensure the targeted irradiation conditions are met is provided. Specimens were configured as small disks, compact tension specimens and tensile bars to facilitate post-irradiation examination (PIE) that will include mechanical testing, microstructure characterization, and fracture toughness testing. Given the considerations for ASTM standardized mechanical testing, comparative fluence and temperature across specimen pairs, and comprehensive PIE planning herein, this work serves as a template for future nuclear materials qualification experiment designs.