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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 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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Latest News
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.
A. R. Raffray, F. Escourbiac, F. J. Fuentes, L. Giancarli, B. Macklin, A. Martin, M. Merola, R. Mitteau, J. Palmer
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 465-476
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-945
Articles are hosted by Taylor and Francis Online.
The overall programmatic objective of ITER is to demonstrate the scientific and technological feasibility of fusion energy for peaceful purposes. The physics part of this objective (including burning plasma, Q of at least 10 and stationary conditions) seems to be well appreciated by the scientific community internationally. However, there seems to be less of an emphasis on the fusion technology part of the objective, which includes demonstrating the availability and integration of technologies essential for a fusion reactor and testing components including tritium breeding blanket modules for a future reactor. In fact important technology information will be obtained from the design, fabrication and operation of the vacuum vessel and out-of-vessel systems such as magnets, tritium system, cryogenic systems, cooling water systems, and associated safety aspects. In addition, DEMO-relevant information will be obtained from the operation of breeding blanket test modules in ITER. Moreover valuable information applicable to DEMO and beyond will also be obtained in a number of areas linked to in-vessel components. This paper summarizes the DEMO-relevant fusion technology information that will be obtained from ITER with a major focus on the areas linked to in-vessel components.