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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.
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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.
Kaushik Chatterjee, Mohammad Modarres
Nuclear Science and Engineering | Volume 170 | Number 2 | February 2012 | Pages 136-150
Technical Paper | doi.org/10.13182/NSE11-27
Articles are hosted by Taylor and Francis Online.
In probabilistic safety assessments of pressurized water reactors, it is imperative to assess the potential and frequency of steam generator tube ruptures. Estimation of the frequency of steam generator tube ruptures has traditionally been based on historical occurrences, which are not applicable to new designs of steam generators with different geometries, material properties, degradation mechanisms, and thermal-hydraulic behaviors. This paper presents a new probabilistic mechanistic-based approach for estimating steam generator tube rupture frequency that is based on the principle that the failure of passive systems is governed by degradation or unfavorable conditions created through the underlying operating conditions and underlying mechanical, electrical, thermal, and chemical processes. This developed approach identifies, probabilistically models, and simulates potential degradations in new and existing steam generator designs to assess degradation versus time, until such degradation exceeds a known endurance limit. An example application of the proposed reliability prediction approach is presented for a new design of small modular reactor steam generators consisting of helically coiled tubes fabricated with advanced tube materials. This developed probabilistic physics-of-failure-based approach, when combined with probabilistic safety assessment techniques, can provide an effective tool for the evaluation of the safety and reliability of steam generators, particularly new steam generator designs used in advanced reactors.