Loss-of-Flow and Loss-of-Pressure Simulations of the BR2 Research Reactor with HEU and LEU Fuel

Loss-of-Flow and Loss-of-Pressure Simulations of the BR2 Research Reactor with HEU and LEU Fuel [electronic resource]

Belgian Reactor 2 (BR2) is a research and test reactor located in Mol, Belgium and is primarily used for radioisotope production and materials testing. The Materials Management and Minimization (M3) Reactor Conversion Program of the National Nuclear Security Administration (NNSA) is supporting the c...

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Bibliographic Details
Online Access: Online Access (via OSTI)
Corporate Author: Argonne National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : United States. National Nuclear Security Administration ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 2016.
Subjects:
Highly Enriched Uranium.
Br-2 Reactor.
Loss Of Flow.
Depressurization.
Slightly Enriched Uranium.
Nuclear Fuels.
Safety Analysis.
Reactor Accident Simulation.
Thermal Hydraulics.
Conversion.
Configuration.
Reactor Cores.
Transients.
General Studies Of Nuclear Reactors.
Description
Summary:Belgian Reactor 2 (BR2) is a research and test reactor located in Mol, Belgium and is primarily used for radioisotope production and materials testing. The Materials Management and Minimization (M3) Reactor Conversion Program of the National Nuclear Security Administration (NNSA) is supporting the conversion of the BR2 reactor from Highly Enriched Uranium (HEU) fuel to Low Enriched Uranium (LEU) fuel. The reactor core of BR2 is located inside a pressure vessel that contains 79 channels in a hyperboloid configuration. The core configuration is highly variable as each channel can contain a fuel assembly, a control or regulating rod, an experimental device, or a beryllium or aluminum plug. Because of this variability, a representative core configuration, based on current reactor use, has been defined for the fuel conversion analyses. The code RELAP5/Mod 3.3 was used to perform the transient thermal-hydraulic safety analyses of the BR2 reactor to support reactor conversion. The input model has been modernized relative to that historically used at BR2 taking into account the best modeling practices developed by Argonne National Laboratory (ANL) and BR2 engineers.
Item Description:Published through SciTech Connect.
01/01/2016.
"anl/rtr/tm--15/8"
"130470"
J. Licht; A. Bergeron; B. Dionne; E. Sikik; G. Van den Branden; E. Koonen.
Physical Description:82 p. : digital, PDF file.

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