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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.
Hatice Akkurt, Naeem M. Abdurrahman
Nuclear Technology | Volume 127 | Number 3 | September 1999 | Pages 301-314
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A3003
Articles are hosted by Taylor and Francis Online.
In 1967, a series of critical experiments were conducted at the Westinghouse Reactor Evaluation Center under the joint sponsorship of the Empire State Atomic Development Associates (ESADA) and Westinghouse using mixed-oxide (MOX) fuel. During the experimental program, both single- and multiregion critical core configurations were constructed for different fuel types and lattice pitches. Two types of MOX fuels and a low-enriched UO2 fuel were used. A description of selected single-region ESADA experiments with criticality benchmark calculation results for those experiments as well as sensitivity analysis results on some configurations is given. Criticality calculations were performed using MCNP-4A with both ENDF/B-V and ENDF-B/VI cross-section libraries. The calculational results show that the calculated eigenvalues with ENDF/B-V cross-section libraries are higher than calculated eigenvalues with ENDF/B-VI cross-section libraries for all types of fuel. Calculational results also indicate that there is an increase in keff with increasing lattice pitch with both cross-section libraries. The uncertainties in keff value due to some uncertainties in the measured data are also calculated.