ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
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.
T. D. Bohm, B. Smith, M. E. Sawan, P. P. H. Wilson
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 703-707
Nuclear Analysis & Experiments | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST11-A12467
Articles are hosted by Taylor and Francis Online.
The surface source write/read capability in the 3-D neutronics code MCNP has been implemented in the CAD based DAG-MCNP. We performed neutronics calculations for a detailed solid model of an ITER first wall/shield module to assess the accuracy of the results obtained using the surface source for toroidal fusion systems. To further understand the sensitivity of the results to the size of the surface source and boundary conditions, we performed calculations for a simplified 3-D ITER model. The results show that use of the surface source approach is accurate provided that the surface source and associated reflective boundaries are extended beyond the component of interest by at least 10 cm and the surface source is generated/placed as close as possible to the front surface of that component.
