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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
Daisuke Kawasaki, Joonhong Ahn, Paul L. Chambré, William G. Halsey
Nuclear Technology | Volume 148 | Number 2 | November 2004 | Pages 181-193
Technical Paper | High-Level Radioactive Waste Disposal | doi.org/10.13182/NT04-A3558
Articles are hosted by Taylor and Francis Online.
Results are presented of an analytical study of mass release of a long-lived radionuclide from multiple waste canisters placed in a water-saturated repository in a two-dimensional array configuration. The radionuclide is assumed to be released congruently with the dissolution of the waste matrix. The concentration and release rate of the radionuclide from the downstream side of the repository region are numerically calculated to observe the effects of canister multiplicity and the leach time of the waste form. Peak values of the concentration and the release rate have been analytically formulated.For numerical illustration, the case of a Japanese repository concept is considered, where canisters containing vitrified wastes are placed in a water-saturated granitic rock. For the illustration, the nuclide 135Cs is chosen, which is characterized by a long half-life and high mobility in the assumed geologic media.The peak exit concentration becomes independent of the number of waste canisters in the flow direction if the number is sufficiently great. This peak value is a theoretical upper bound of the exit concentration, regardless of the number of canisters or the waste matrix leach time. The model is suitable for assisting in the design of a repository since the effects of the canister array configuration are reflected by the peak exit concentration and the peak release rate.