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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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Latest News
Workshop highlights commercial fabrication of universal waste canister
Deep Isolation announced that it hosted its third technical workshop for the UPWARDS project, a Department of Energy Advanced Research Projects Agency-Energy (ARPA-E) initiative aimed at developing a universal canister system (UCS) for the disposal of radioactive waste streams from advanced reactors. The workshop, held at R-V Industries in Honey Brook, Pa., focused on the large-scale manufacturing and commercialization of the UCS.
Charles S. Olsen, Richard R. Hobbins, Beverly A. Cook
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 884-896
Technical Paper | TMI-2: Decontamination and Waste Management / Material | doi.org/10.13182/NT89-A27682
Articles are hosted by Taylor and Francis Online.
Examinations of the core debris from the damaged Three Mile Island Unit 2 (TMI-2) core were an important part of the overall understanding of the accident. Results from carefully designed in-pile and out-of-pile experiments were necessary for the evaluation of the core materials. In particular, results from the Power Burst Facility severe fuel damage tests conducted at the Idaho National Engineering Laboratory and unirradiated fuel bundle tests and out-of-pile materials interaction experiments conducted at Kernforschungszentrum Karlsruhe in the Federal Republic of Germany have been used to help characterize the core materials from TMI-2. The application of the results of these experiments to the characterization of the core debris for the TMI-2 accident evaluation is described.