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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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.
Ihor O. Bohachevsky, Ronald N. Kostoff
Fusion Science and Technology | Volume 2 | Number 4 | October 1982 | Pages 687-699
Technical Paper | Blanket Engineering | doi.org/10.13182/FST82-A20807
Articles are hosted by Taylor and Francis Online.
Cyclic thermal loads and stresses in two critical components of fusion reactors, including fusion-fission hybrids, are modeled and calculated. The two critical components are the solid wall adjacent to the fusion plasma (“first wall”) and the fissile fuel elements in the high-power density region of the blanket. These two components exemplify two limiting cases of thermal loading: The first-wall loads are generated by predominantly shallow energy deposition that may be approximated with a flux across the surface and the fuel elements loads are generated by volumetric heating. Two approaches are used to solve the heat conduction equation and to calculate the resulting stresses in terms of system parameters. The first is expansion into Fourier series and determination of periodic solutions; the second is analysis and superposition of single-pulse responses weighted with appropriate time delay and decay factors. Approximate closed-form expression for temperature excursions and thermal stresses are derived; these expressions may be evaluated conveniently and rapidly for comparison of different systems. The results provide a quantitative basis for trade-off studies and comparative assessments of different fusion reactor systems.