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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
DOE issues final RFQ for WIPP clean energy initiative
The Department of Energy’s Office of Environmental Management has issued a request for qualifications for interested parties and prospective offerors looking to enter into a realty agreement for carbon-pollution-free electricity (CFE) projects at the department’s Waste Isolation Pilot Plant site in southeastern New Mexico.
Taichi Matsumura, Ryuji Nagaishi, Jun-ichi Katakura, Masahide Suzuki
Nuclear Science and Engineering | Volume 192 | Number 1 | October 2018 | Pages 70-79
Technical Paper | doi.org/10.1080/00295639.2018.1493856
Articles are hosted by Taylor and Francis Online.
In order to evaluate three-dimensional distributions of radionuclides with high precision from gamma-scanning profiles of adsorption vessels used for decontamination of radioactive water performed at severe accidents, gamma scanning of the submerged demineralizer system vessel at the Three Mile Island Unit 2 (TMI-2) accident was simulated in the axial and radial directions of real and cylindrical-shaped vessels using a Monte Carlo calculation code [Particle and Heavy Ion Transport Code System (PHITS)].
In the axial simulation, the true distribution of radioactive 137Cs in the zeolite packed bed of the vessel was successfully evaluated when a correction function derived from a virtual constant distribution of 137Cs was applied to the reported gamma-scanning profile. In the radial simulation, the virtual disk-formed and shell-formed sources of 137Cs displaced in the packed bed were clearly observed from the top and bottom views of the vessel. This new radial gamma scanning indicates that the radial localization of 137Cs could be well observed by measuring the gamma ray from the top view of the vessel during storage. Further, the radial gamma scanning from the side view and whether or not the radial localization of 137Cs can be confirmed in the normally existing gamma-scanning room were examined.