Development of a Graphical User Interface for In-Core Fuel Management Using MCODE
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 an...
| Main Authors: | , , |
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| Other Authors: | |
| Format: | Article |
| Language: | en_US |
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American Nuclear Society
2013
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| Online Access: | http://hdl.handle.net/1721.1/77152 https://orcid.org/0000-0003-1459-7672 https://orcid.org/0000-0002-1147-045X |
| _version_ | 1811069205775122432 |
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| author | Romano, Paul Kollath Newton, Thomas H., Jr. Forget, Benoit Robert Yves |
| author2 | Massachusetts Institute of Technology. Department of Nuclear Science and Engineering |
| author_facet | Massachusetts Institute of Technology. Department of Nuclear Science and Engineering Romano, Paul Kollath Newton, Thomas H., Jr. Forget, Benoit Robert Yves |
| author_sort | Romano, Paul Kollath |
| collection | MIT |
| description | 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. |
| first_indexed | 2024-09-23T08:07:23Z |
| format | Article |
| id | mit-1721.1/77152 |
| institution | Massachusetts Institute of Technology |
| language | en_US |
| last_indexed | 2024-09-23T08:07:23Z |
| publishDate | 2013 |
| publisher | American Nuclear Society |
| record_format | dspace |
| spelling | mit-1721.1/771522023-02-26T02:25:52Z Development of a Graphical User Interface for In-Core Fuel Management Using MCODE Romano, Paul Kollath Newton, Thomas H., Jr. Forget, Benoit Robert Yves Massachusetts Institute of Technology. Department of Nuclear Science and Engineering MIT Nuclear Reactor Laboratory Forget, Benoit Romano, Paul Kollath Forget, Benoit Newton, Thomas H., Jr. 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. 2013-02-15T19:23:12Z 2013-02-15T19:23:12Z 2009-04 Article http://purl.org/eprint/type/ConferencePaper 9780894480683 0894480685 http://hdl.handle.net/1721.1/77152 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. https://orcid.org/0000-0003-1459-7672 https://orcid.org/0000-0002-1147-045X en_US Proceedings of Advances in Nuclear Fuel Management IV (ANFM 2009) 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. application/pdf American Nuclear Society Romano |
| spellingShingle | Romano, Paul Kollath Newton, Thomas H., Jr. Forget, Benoit Robert Yves Development of a Graphical User Interface for In-Core Fuel Management Using MCODE |
| title | Development of a Graphical User Interface for In-Core Fuel Management Using MCODE |
| title_full | Development of a Graphical User Interface for In-Core Fuel Management Using MCODE |
| title_fullStr | Development of a Graphical User Interface for In-Core Fuel Management Using MCODE |
| title_full_unstemmed | Development of a Graphical User Interface for In-Core Fuel Management Using MCODE |
| title_short | Development of a Graphical User Interface for In-Core Fuel Management Using MCODE |
| title_sort | development of a graphical user interface for in core fuel management using mcode |
| url | http://hdl.handle.net/1721.1/77152 https://orcid.org/0000-0003-1459-7672 https://orcid.org/0000-0002-1147-045X |
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