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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Fusion Science and Technology
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
R. T. McGrath, A. J. Russo, R. B. Campbell, R. D. Watson
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1805-1816
Plasma-Facing Component | doi.org/10.13182/FST92-A29981
Articles are hosted by Taylor and Francis Online.
Tokamaks currently in operation deposit on the order of 1–30 MW/m2 onto plasma facing surfaces during normal operation and hundreds of MW/m2 for shorter periods of time (0.1–3 ms) during disruptions. Disruption deposited energies on future high-power tokamaks may be well in excess of 20 MJ/m2 Design of plasma facing components (PFCs) for such severe environments requires considerable advancements in materials development, armor tile bonding to actively cooled substrates, heat transfer, and many other areas of engineering concern. Considerable improvements in PFC performance, reliability and lifetime can also be accomplished through improved understanding and control of the edge plasma boundary layer. This paper covers both engineering and edge plasma physics issues that must be addressed in the development of reliable PFCs for ITER. Several specific examples are addressed since a complete treatment of all critical development issues would be lengthy. Topics covered include impurity generation and transport in the boundary layer plasma, materials response to intense pulsed disruption heat loads, runaway electron generation during disruptions, high heat flux performance and PFC fabrication issues. These topics are illustrative examples of the variety of complex issues that must be addressed in the development and design of PFCs.