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August 24–27, 2026
Dallas, TX|Hilton Anatole
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Launching into tomorrow: NRIC guides new era of research and deployment
In June 2025, the Department of Energy announced the Reactor Pilot Program, an authorization pathway that allowed reactor developers to partner with the DOE to get first-of-a-kind (FOAK) reactors built and tested. Soon after, the DOE rolled out a complementary Fuel Line Pilot Program, which aimed to fast-track fuel projects. In all, 20 projects were accepted into the new programs.
A. E. Pickett, W. L. Pearl, M. C. Rowland
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 453-461
Technical Paper | doi.org/10.13182/NT65-A20557
Articles are hosted by Taylor and Francis Online.
Nonsensitized Type-304 stainless-steel fuel cladding cracked intergranularly when exposed to high-temperature, high-purity, water reactor environments. Similar failures were produced out of reactor in stressed tubular-capsule specimens exposed to dilute solutions of iron chloride, copper chloride, sodium hydroxide, and chromic acid at 650° F (343°C). An iron chloride test was developed that closely simulates the intergranular attack on stressed nonsensitized Type-304 stainless-steel fuel cladding. Stressed, cold-worked, nonsensitized Type-304 stainless-steel tubing cracked in less than 24 h at 650° F when exposed to ferric-ferrous chloride solutions containing only 40 Cl parts/106 and 4 soluble-iron parts/106. Exposure at 650° F caused intergranular cracking only, while exposure at 550° F (288° C) caused mixed transgranular and intergranular cracking. The accelerated autoclave test can be used for screening of prospective cladding materials and alloy modifications and developing a better understanding of the mechanism of attack.