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Latest News
INL makes first fuel for Molten Chloride Reactor Experiment
Idaho National Laboratory has announced the creation of the first batch of enriched uranium chloride fuel salt for the Molten Chloride Reactor Experiment (MCRE). INL said that its fuel production team delivered the first fuel salt batch at the end of September, and it intends to produce four additional batches by March 2026. MCRE will require a total of 72–75 batches of fuel salt for the reactor to go critical.
S. L. Robinson, N. Y. C. Yang
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 856-860
Material; Storage and Processing | doi.org/10.13182/FST92-A29856
Articles are hosted by Taylor and Francis Online.
The effects of internal tritium and helium on the tensile properties of two austenitic stainless steels and an iron-based superalloy have been studied. The materials tested were, forged 21Cr-6Ni-9Mn and 304L (tested in the annealed condition and two forged conditions), and a modified A-286 alloy. The accumulation of 3He from the radioactive decay of tritium caused an increase in the yield strength and a continuous decrease in the ductility in almost all materials tested. Increased 3He concentrations also caused a change in fracture mode from ductile rupture to predominantly intergranular fracture. The property changes resulted from 3He bubble-induced strengthening, which produced a change in deformation mode from long-range dislocation activity to deformation twinning. In the deformation-twinning mode, the 3He-accelerated fracture initiated at the intersections of deformation twins with grain boundaries. High-strength forged 304L was most resistant to 3He effects, owing to the redistribution of 3He on dislocations.
