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Fusion Science and Technology
NRC schedules webinars on Holtec’s proposed New Mexico storage site
The Nuclear Regulatory Commission has scheduled four webinars in late August and early September to present its draft environmental findings and receive comments on Holtec International’s proposed consolidated spent nuclear fuel storage facility in New Mexico. Webinars were previously held on June 23 and July 9.
As published in the August 13 Federal Register, the public comment webinars will be held on August 20 from 6–9 p.m., August 25 from 2–5 p.m., August 26 from 6–9 p.m., and September 2 from 11 a.m.–2 p.m. All times are Eastern. Information for the webinars is posted on the NRC’s Public Meetings webpage.
G. R. Longhurst, G. A. Deis, P. Y. Hsu, L. G. Miller, R. A. Causey
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 681-686
Tritium | dx.doi.org/10.13182/FST83-A22938
Articles are hosted by Taylor and Francis Online.
Experimental evidence collected by several researchers suggests that gamma radiation may enhance the release of tritium from structural materials in fusion reactors. If so, this may reduce inventories and, in first walls, it may reduce permeation rates. The release process is not well understood, but it appears to involve Compton scattering of photons by electrons of the host material. The excited electrons then interact with binding potential fields to effect the release of bound tritium atoms. This process seems to be fairly efficient in nonmetals where it may result in enhanced diffusion, but it should be less important than thermal processes in metals. Experiments were conducted in the gamma irradiation facility of the Advanced Test Reactor at the Idaho National Engineering Laboratory to determine whether gamma radiation has an appreciable effect on the normal permeation of tritium through stainless steel. Low concentrations of HT were allowed to diffuse through a 0.071-cm-thick tube of 316 stainless steel, heated between 590 and 733 K. Gamma irradiation intensities were varied from 1.3 to 155 C/kgh (5 × 103 to 6 × 105 R/h). Ion chamber detectors were used to measure tritium concentrations on both sides of the tube. It was found that in the presence of excess H2, the higher gamma irradiation intensity exhibited slightly higher permeation rates of tritium. When the walls of the permeation tube and the HT were highly oxidized, the permeation rates were much more scattered, and the gamma irradiation seemed to have no observable effect. It was concluded that the effect of gamma radiation on tritium permeation through stainless steel in a fusion reactor environment should be small. However, the relative ease with which tritium from HTO was seen to permeate the material raises questions regarding tritium management in breeder blankets.