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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.
P. Chellapandi, S. C. Chetal, Baldev Raj
Nuclear Technology | Volume 172 | Number 1 | October 2010 | Pages 1-15
Technical Paper | Fission Reactors | doi.org/10.13182/NT10-A10878
Articles are hosted by Taylor and Francis Online.
The FUSTIN dedicated computer code has been developed to predict the transient response of pool-type fast reactor components in a core disruptive accident. FUSTIN accurately simulates several complex phenomena, such as large distortions in the fluids, large displacements of the structure, fast transient fluid-structure interaction, etc., involved in determining the transient pressures, vessel displacements, and strains. FUSTIN has been validated by solving a few international benchmark problems. Further, for experimental validation of FUSTIN, dedicated tests were conducted to (a) characterize a low-density explosive that can appropriately simulate the nuclear energy release rate and (b) generate data, particularly deformations in the vessels representing the scaled-down model of the main vessel of a typical pool-type fast reactor. In the tests, the nuclear energy release rate was simulated by a low-density chemical explosive, which has been thoroughly characterized. The validation exercise demonstrates the excellent prediction capability of FUSTIN. The paper presents the mathematical formulations, solution strategy, and validation aspects of FUSTIN.