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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.
Abdelfatah Abdelmaksoud, Hesham Elbakhshawangy, Mohamed Abdelaziz
Nuclear Technology | Volume 209 | Number 6 | June 2023 | Pages 857-871
Technical Paper | doi.org/10.1080/00295450.2022.2158667
Articles are hosted by Taylor and Francis Online.
In the present work, a numerical study of inward and outward buckling of two successive fuel plates of a typical material testing reactor is investigated using computational fluid dynamics code. Fuel plate buckling results in partial blockage of the hot channel. Both buckling toward the inside and outside are considered. Simulations are conducted for different blockage levels of the nominal flow area, i.e., 0%, 20%, 40%, 50%, 60%, and 70% for inward buckling. Blockage levels of 0%, 20%, 40%, 50%, 60%, 70%, 80%, and 90% are considered for outward buckling. The impact of the flow field redistribution in four successive channels on the cooling capacity of each channel is investigated. The obtained results show that for an inward buckling ratio greater than 50%, critical phenomena will occur that could affect the clad integrity. Moreover, for inward buckling of 70%, the maximum clad temperature in the blocked channel reaches the value associated with the onset of nucleate boiling at the operating pressure. On the other hand, for outward buckling of 90%, critical phenomena that could affect the clad integrity will occur.