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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.
Ling Zou, Hongbin Zhang, Jess Gehin, Brendan Kochunas
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 535-542
Technical Paper | Fission Reactors / Thermal Hydraulics | doi.org/10.13182/NT13-A19440
Articles are hosted by Taylor and Francis Online.
A thermal-hydraulics (TH)/neutronics/crud multiphysics coupling framework to simulate the crud deposits' impact on crud-induced power shift (CIPS) phenomenon is proposed in this paper. The coupling among three essential physics (i.e., TH, crud, and neutronics) was implemented by coupling the computational fluid dynamics software STAR-CCM+, a newly developed crud module, and the neutronics code DeCART. A typical 3 × 3 pressurized water reactor fuel pin problem was analyzed with this framework and simulation results are presented. Time-dependent results are provided for a 12-month simulation. Simulation results provide the history of crud deposits inventory and their distributions on fuel rods, boron hideout amount inside crud deposits, and power shape changing over time. The obtained results clearly showed the power shape suppression in regions where crud deposits exist, a clear indication of CIPS phenomenon.
