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dc.contributor.authorRomano, Paul Kollath
dc.contributor.authorNewton, Thomas H., Jr.
dc.contributor.authorForget, Benoit Robert Yves
dc.date.accessioned2013-02-15T19:23:12Z
dc.date.available2013-02-15T19:23:12Z
dc.date.issued2009-04
dc.identifier.isbn9780894480683
dc.identifier.isbn0894480685
dc.identifier.urihttp://hdl.handle.net/1721.1/77152
dc.description.abstractIn 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.en_US
dc.language.isoen_US
dc.publisherAmerican Nuclear Societyen_US
dc.rightsArticle is made available in accordance with the publisher's policy and may be subject to US copyright law. Please refer to the publisher's site for terms of use.en_US
dc.sourceRomanoen_US
dc.titleDevelopment of a Graphical User Interface for In-Core Fuel Management Using MCODEen_US
dc.typeArticleen_US
dc.identifier.citationRomano, 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.en_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineeringen_US
dc.contributor.departmentMIT Nuclear Reactor Laboratoryen_US
dc.contributor.approverForget, Benoit
dc.contributor.mitauthorRomano, Paul Kollath
dc.contributor.mitauthorForget, Benoit
dc.contributor.mitauthorNewton, Thomas H., Jr.
dc.relation.journalProceedings of Advances in Nuclear Fuel Management IV (ANFM 2009)en_US
dc.eprint.versionAuthor's final manuscripten_US
dc.type.urihttp://purl.org/eprint/type/ConferencePaperen_US
dspace.orderedauthorsRomano, Paul K.; Forget, Benoit; Newton, Thomas H., Jr.en_US
dc.identifier.orcidhttps://orcid.org/0000-0003-1459-7672
dc.identifier.orcidhttps://orcid.org/0000-0002-1147-045X
mit.licensePUBLISHER_POLICYen_US
mit.metadata.statusComplete


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