Tensile properties of candidate SNS target container materials after proton and neutron irradiation in the LANSCE accelerator

Temperature effects on the mechanical properties of candidate SNS target container materials after proton and neutron irradiation

“…The data indicated that the additional hardening effect from helium (hydrogen) bubbles became significant at helium concentrations above 1 at.%. In the spallation condition, the helium concentration at the highest dose of 11 dpa was about 0.1 at.% [3][4][5]. Thus, some strengthening contribution due to the presence of the gases is expected at the highest dose.…”

“…3 and 4 the tensile data for current EC316LN specimens are overlaid on the trend bands of the database for 316 stainless steels irradiated at temperatures between room temperature and 200°C in fission reactors and tested in the same temperature range [17]. Further, the data are compared with the previous room temperature data for candidate SNS target container materials irradiated in neutron (n) or proton (p) areas of the LANSCE-APT irradiation [2][3][4][5]. At doses below about 1 dpa both yield strength and uniform elongation data for LANSCE irradiations are compatible with the trend bands of the database.…”

“…A goal exposure for the first target is six months operation, corresponding to a displacement dose of about 5 dpa in the container vessel. In earlier reports [2][3][4][5][6][7] we described the tensile properties of candidate vessel materials after irradiation in the Los Alamos Neutron Scattering Center (LANSCE) accelerator at Los Alamos National Laboratory (LANL) at temperatures in the range 58-160°C. The tensile tests were conducted at ORNL at room temperature.…”

“…Austenitic stainless steels showed the most satisfactory results. They retained significant ductility even after irradiation to 11 dpa; the EC316LN steel had positive work hardening and a uniform elongation of 6% [2,5]. Ferritic/martensitic steels displayed prompt instability failures at yield.…”

In-situ Creep Testing Capability Development for Advanced Test Reactor

“…They show no significant shift of ductile to brittle transition temperature by irradiation at low temperatures (below 400°C), although they show low resistance to irradiation swelling and creep above about 400°C. 27 These steels have been not only widely used in conventional nuclear power plants, where operation temperatures are limited below 400°C, but are also selected for advanced reactor components such as the first wall and shield of ITER 28 and the container vessel for the liquid metal target of the spallation neutron source [27][28][29][30] . Table 3-5 also summarizes the fabrication processes and heat treatments applied to specimen data presented in this section.…”