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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
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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 B. Abramson
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 195-214
Technical Paper | doi.org/10.13182/NSE77-A26957
Articles are hosted by Taylor and Francis Online.
Subroutine POOL was developed for the study of hypothetical core disruptive accidents in nuclear reactors and, as such, is set up for use as a subroutine in the FX-2 Dynamic Neutronics Code. This combination permits scoping studies of the total neutronic/hydrodynamic interactions and is capable of performing phenomenological investigations of hypothetical problems ranging from the high ramp disassembly calculations, performed in the past by the Lagrangian code VENUS, to the study of recriticality in boiling pools of fuel and steel. POOL specifically includes, in at least parametric fashion, the following phenomena: 1. intra- and inter-element heat transfer by diffusion, convection, and radiation for both fuel and steel inside the pool and at the boundaries 2. local vapor generation and concurrent local pressurization 3. hydrodynamic behavior using the inviscid Navier-Stokes equations in a Eulerian formulation. Sample results are shown for boil-up of an initially quiescent dense pool of fuel and steel. Subroutine POOL was modified by removing the free surface portion of the calculation and the associated expansion of the Eulerian Grid. The combined code, known as FX2-P00L, was used to perform prompt burst calculations for two comparison cases for a lOOO-MW(th) demolike reactor. Good agreement is shown between FX2-POOL and VENUS II for these two hypothetical situations, indicating that the hydrodynamic and thermodynamic assumptions made in POOL are accurate enough for prompt burst analysis and compare well with the VENUS models.