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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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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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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.
A. Robinson, L. El-Guebaly, D. Henderson
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 720-724
Nuclear Analysis & Experiments | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST11-A12470
Articles are hosted by Taylor and Francis Online.
Every few years, maintenance will be required to replace the plasma facing components of any fusion power plant. To come up with a realistic maintenance scheme, an accurate method of evaluating the biological dose rate is needed. In some studies, the simple and quick approach of the contact dose rate for a specific component was used to estimate the biological dose rate. This method doesn't take radiation from nearby components into account and the accuracy of its methodology is questionable. The more accurate multi-step method, which involves transporting the delayed gammas from induced activation in the forward or adjoint mode, is able to take radiation from all surrounding components into account. In this report, the biological dose rate was evaluated with the adjoint method at selected radial locations of ARIES-CS, and then compared to the contact dose rate of the nearest component to determine the accuracy of the contact dose method. Our results indicate that the approximate contact dose rate could be off by an order of magnitude.