Development of a Graphical User Interface for In-Core Fuel Management Using MCODE
Name
ANFM Final Paper v1.pdf
Description
Main article
Size
661.53 KB
Format
Adobe PDF
Checksum (MD5)
f9be6210e758efe267b3d0b75505f875
Author(s)
Romano, Paul Kollath
Newton, Thomas H., Jr.
Forget, Benoit Robert Yves
Date Issued
April 2009
Journal
Proceedings of Advances in Nuclear Fuel Management IV (ANFM 2009)
Publisher
American Nuclear Society
Citation
Romano, Paul K., Benoit Forget, and Thomas H. Newton, Jr. "DEVELOPMENT OF A GRAPHICAL USER INTERFACE FOR IN-CORE FUEL MANAGEMENT USING MCODE." Advances in Nuclear Fuel Management IV (ANFM 2009) Hilton Head Island, South Carolina, USA, April 12-15, 2009, American Nuclear Society, LaGrange Park, IL (2009). p.1-13.
Version
Author's final manuscript
Abstract
In the present work, a graphical user interface is developed to automate in-core fuel management using MCODE, an MCNP-ORIGEN linkage code. Data abstraction is achieved by means of five object classes that define the run, fuel assembly locations, fuel assemblies, fuel paths, and materials. The GUI and an associated fuel management wrapper were developed in Python, with the PyQt extension being used for GUI-specific features. To validate the fuel management wrapper, a model of the MIT Reactor core was used to run an equilibrium core. The results show that the wrapper performs reliably. Together, these tools will help the staff at the MITR perform in-core fuel management calculations quickly and with a higher level of detail than that previously possible.
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
MIT Nuclear Reactor Laboratory
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