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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.
R. A. Borrelli, Joonhong Ahn
Nuclear Technology | Volume 164 | Number 3 | December 2008 | Pages 442-464
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT08-A4037
Articles are hosted by Taylor and Francis Online.
A scoping study is presented in order to investigate the potential of bentonite extrusion on radionuclide transport in a water-saturated planar fracture. A coupled mathematical model for an abstracted case describing the mass conservation of radionuclides and bentonite extrusion into the fracture is established to observe the mass transport phenomena due to bentonite extrusion in the fracture domain. Results of numerical simulations are then analyzed in order to interpret the potential importance of extrusion in the near-field rock on the overall performance of the engineered barrier system (EBS). The mathematical model developed in this study for radionuclide migration incorporates spatial and temporal changes in porosity due to movement of bentonite particles. Finite element solutions have been derived for the porosity and for the radionuclide concentration.With a sufficiently strong sorption, the radionuclide is observed to be contained within the region of bentonite extrusion, indicating that radionuclides would be retained within the extrusion region even if the waste canister fails early while bentonite is extruding in fractures. Such results imply the potential of the extrusion region to enhance performance in the EBS and warrant more rigorous modeling studies of this domain.
