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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
E. Eidelpes, L. F. Ibarra (Univ of Utah), R. A. Medina (Univ of New Hampshire)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 195-205
The work presented in this paper is part of investigations on the structural integrity of Spent Nuclear Fuel (SNF) casks after long-term storage and subjected to normal or accidental conditions of transport. The main challenge of this assessment is to account for the time dependent material degradation mechanisms of the cask components. A Probabilistic Risk Assessment (PRA) is used for the overall assessment of the structural integrity of the relevant package components. SNF rod cladding is likely to control structural failure due to mechanical loads, which can be accelerated by hydride related material degradation of fuel rods after long-term storage. Due to limited available experimental data, statistical methods are used to predict the fuel rod conditions between beginning of storage and moment of transport. The value of the Rod Internal Pressure (RIP) appears to be a driving force for the hydride-induced embrittlement. RIP examination data and recent simulations point towards relatively low Cladding Hoop Stresses (CHSs) in standard rods during drying procedures. An exemplary PRA of the likelihood of cladding embrittlement due to Radial Hydride Reorientation (RHR) is presented. The preliminary model indicates a relatively low probability of cladding embrittlement for standard fuel rods.
