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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
Paul W. Fisher
Fusion Science and Technology | Volume 21 | Number 2 | March 1992 | Pages 794-799
Material; Storage and Processing | doi.org/10.13182/FST92-A29845
Articles are hosted by Taylor and Francis Online.
The tritium proof-of-principle (TPOP) experiment was designed and built by Oak Ridge National Laboratory (ORNL) to demonstrate the formation and acceleration of the world's first tritium pellets for fueling of future fusion reactors. Many parameters measured during the course of the experiment have been used to evaluate the physical properties of solid tritium. Pellet size was measured as a function of equilibrium fill pressure. A model was developed to predict this information from values of thermal conductivity, vapor pressure, and density reported in the literature. Good agreement between theory and experiment was found for both deuterium and tritium pellets. Evaluation of breakaway pressure data for deuterium pellets indicates that the shear strength of deuterium is about equal to its ultimate tensile strength. Tritium shear strength appears to be about twice that of deuterium at temperatures around 8 K. The reduction in pellet diameter due to barrel erosion for deuterium was about twice that for tritium pellets at a given velocity. This was also indicative of the greater strength of tritium relative to deuterium.