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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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Latest News
Leak-tightness test on deck for SRS mega unit
The Savannah River Site in South Carolina will begin a leak-tightness test to qualify the megavolume Saltstone Disposal Unit (SDU) 10 to store up to 33 million gallons of solidified, decontaminated salt solution produced at the site.
M. Grounes
Nuclear Technology | Volume 5 | Number 4 | October 1968 | Pages 228-235
Technical Paper and Note | doi.org/10.13182/NT68-A28024
Articles are hosted by Taylor and Francis Online.
The susceptibility to irradiation effects in different heats of the same steel and in parts of a reactor vessel that had gone through different stages in the manufacturing process was investigated. Fourteen sets of miniature impact specimens of Uddeholm UHB 2103/R3 steel, the pressure vessel material of the Ågesta reactor, were irradiated at 235 ± 15°C to a neutron fluence of 4 × 1018 − 1019 n/cm2 (>1 MeV). The results indicate that there might be a difference by a factor of 2 in irradiation-induced transition temperature increases between materials from different parts of the vessel. Generally, changes in the hot-pressed material seemed to be larger. If irradiation-damage studies are performed on flat, normalized plate, the results are valid if an extra safety margin of 30°C is applied.