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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
Standards Program
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.
L. Romero, L. Moreno, I. Neretnieks
Nuclear Technology | Volume 112 | Number 1 | October 1995 | Pages 89-98
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT95-A15854
Articles are hosted by Taylor and Francis Online.
Radionuclides leaking from a damaged canister spread into the backfill material surrounding the canister and then migrate through different pathways into water-bearing fractures in the rock surrounding the nuclear waste repository. If the backfill and other materials surrounding the canister have a low permeability, water flow is then excluded from these materials, and the solute transport is by diffusion only. Some nuclides are delayed by sorption on the materials through which they move, and those nuclides with short half-lives may decay to insignificant concentrations before they reach the flowing water in the fractures in the rock. This complex and variable transport geometry is modeled using a compartment model. The NUCTRAN compartment model is a useful tool to calculate the nonstationary transport of single nuclides or radionuclide chains. The model, which is a very coarsely discretized integrated finite difference model, is devised to be very fast and compact by embedding analytical solutions at sensitive points such as entrances and exits from small holes and fractures. The nuclide inventory in the source may be calculated using a solubility limit approach or a congruent dissolution approach. The model is flexible and can easily be adapted to various geometries. NUCTRAN agrees well with models using a very detailed discretization. Accuracy is gained if compartments with very large capacities are subdivided into a few compartments.