dc.contributor.author | Romano, Paul Kollath | |
dc.contributor.author | Newton, Thomas H., Jr. | |
dc.contributor.author | Forget, Benoit Robert Yves | |
dc.date.accessioned | 2013-02-15T19:23:12Z | |
dc.date.available | 2013-02-15T19:23:12Z | |
dc.date.issued | 2009-04 | |
dc.identifier.isbn | 9780894480683 | |
dc.identifier.isbn | 0894480685 | |
dc.identifier.uri | http://hdl.handle.net/1721.1/77152 | |
dc.description.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. | en_US |
dc.language.iso | en_US | |
dc.publisher | American Nuclear Society | en_US |
dc.rights | Article 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.source | Romano | en_US |
dc.title | Development of a Graphical User Interface for In-Core Fuel Management Using MCODE | en_US |
dc.type | Article | en_US |
dc.identifier.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. | en_US |
dc.contributor.department | Massachusetts Institute of Technology. Department of Nuclear Science and Engineering | en_US |
dc.contributor.department | MIT Nuclear Reactor Laboratory | en_US |
dc.contributor.approver | Forget, Benoit | |
dc.contributor.mitauthor | Romano, Paul Kollath | |
dc.contributor.mitauthor | Forget, Benoit | |
dc.contributor.mitauthor | Newton, Thomas H., Jr. | |
dc.relation.journal | Proceedings of Advances in Nuclear Fuel Management IV (ANFM 2009) | en_US |
dc.eprint.version | Author's final manuscript | en_US |
dc.type.uri | http://purl.org/eprint/type/ConferencePaper | en_US |
dspace.orderedauthors | Romano, Paul K.; Forget, Benoit; Newton, Thomas H., Jr. | en_US |
dc.identifier.orcid | https://orcid.org/0000-0003-1459-7672 | |
dc.identifier.orcid | https://orcid.org/0000-0002-1147-045X | |
mit.license | PUBLISHER_POLICY | en_US |
mit.metadata.status | Complete | |