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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. E. Reagan, R. L. Beatty, E. L. Long, Jr.
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 34-41
Technical Paper | doi.org/10.13182/NSE67-A18664
Articles are hosted by Taylor and Francis Online.
Fuel particles coated with pyrolytic carbon are contemplated for use in several high-temperature gas-cooled reactors. This paper describes the performance of pyrolytic carbon-coated, high-density, uranium oxide particles irradiated at 1300 to 1600°C. The fission-gas release, burnups, and temperatures for five experiments are given. Coated particles with a builtin gap between the fuel and the inner laminar coating began to show evidence of failure by releasing bursts of fission gas after 27.9% uranium burnup, and postirradiation examination revealed delamination of the inner coating. Coated particles made with a porous carbon buffer layer between the fuel and an isotropic coating showed no evidence of failure by fission-gas release, and showed no damage due to irradiation when examined by metallography. Coated particles with neither gap nor buffer, but with a low-density inner coating applied directly to the fuel, retained fission gas successfully but showed enlargement of cracks that had formed at the fuel-coating interface during the coating process. The oxide particles did not flow at high burnup and expand into voids and cracks as the carbide particles did, and the oxide did not diffuse into the carbon coating at high temperatures.
