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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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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.
J. W. Kutcher, M. E. Wyman
Nuclear Science and Engineering | Volume 26 | Number 4 | December 1966 | Pages 435-446
Technical Paper | doi.org/10.13182/NSE66-A18414
Articles are hosted by Taylor and Francis Online.
An absolute experimental measurement has been made of the time dependence of the beta energy spectrum from fission fragments, specifically beta particles of energies greater than 0.75 MeV produced in the thermal neutron fission of uranium-235. This measurement has been made for four cases: the initiation of a constant fission rate in a cold uranium foil; shutdown after 1- and 3-h runs at a steady fission rate; and an instantaneous burst of fissions produced by a reactor pulse. The fission source was a foil coated with approximately 38 mg of 235U and placed in a thermal neutron beam from a reactor. The fission rate was measured with an ionization chamber. The beta energy spectrum was measured with a plastic scintillator, with absolute counting being determined by the known solid angle between source and detector. Background counts have been reduced to less than 10% in all cases. The total uncertainty in the analyzed data was less than 5% for the steady power runs and less than 8% for the reactor pulsing runs. The experimental results are in substantial agreement with those predicted by theory.