NUMERICAL MULTIGROUP TRANSIENT ANALYSIS OF SLAB NUCLEAR REACTOR WITH THERMAL FEEDBACK
The paper describes a new numerical code for multigroup transient analyses with thermal feedback. The code is developed at Institute of Nuclear and Physical Engineering. It is necessary to carefully investigate transient states of fast neutron reactors, due to recriticality issues after accident sce...
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| Main Authors: | , , , , , |
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| Format: | Article |
| Language: | English |
| Published: |
Czech Technical University in Prague
2016-12-01
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| Series: | Acta Polytechnica CTU Proceedings |
| Online Access: | https://ojs.cvut.cz/ojs/index.php/APP/article/view/3745 |
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| _version_ | 1849415927049748480 |
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| author | Filip Osuský Branislav Vrban Peter Ballo Štefan Čerba Jakub Lüley Gabriel Farkas |
| author_facet | Filip Osuský Branislav Vrban Peter Ballo Štefan Čerba Jakub Lüley Gabriel Farkas |
| author_sort | Filip Osuský |
| collection | DOAJ |
| description | The paper describes a new numerical code for multigroup transient analyses with thermal feedback. The code is developed at Institute of Nuclear and Physical Engineering. It is necessary to carefully investigate transient states of fast neutron reactors, due to recriticality issues after accident scenarios. The code solves numerical diffusion equation for 1D problem with possible neutron source incorporation. Crank-Nicholson numerical method is used for the transient states. The investigated cases are describing behavior of PWR fuel assembly inside of spent fuel pool and with the incorporated neutron source for better illustration of thermal feedback. |
| format | Article |
| id | doaj-art-59e910c1df4644d990481480e03efdc8 |
| institution | Kabale University |
| issn | 2336-5382 |
| language | English |
| publishDate | 2016-12-01 |
| publisher | Czech Technical University in Prague |
| record_format | Article |
| series | Acta Polytechnica CTU Proceedings |
| spelling | doaj-art-59e910c1df4644d990481480e03efdc82025-08-20T03:33:21ZengCzech Technical University in PragueActa Polytechnica CTU Proceedings2336-53822016-12-0140626710.14311/AP.2016.4.00623359NUMERICAL MULTIGROUP TRANSIENT ANALYSIS OF SLAB NUCLEAR REACTOR WITH THERMAL FEEDBACKFilip Osuský0Branislav Vrban1Peter BalloŠtefan Čerba2Jakub LüleyGabriel FarkasInstitute of Nuclear and Physical Engineering Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology Bratislava, SlovakiaInstitute of Nuclear and Physical Engineering Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology Bratislava, SlovakiaInstitute of Nuclear and Physical Engineering Slovak University of Technology in Bratislava, Faculty of Electrical Engineering and Information Technology Bratislava, SlovakiaThe paper describes a new numerical code for multigroup transient analyses with thermal feedback. The code is developed at Institute of Nuclear and Physical Engineering. It is necessary to carefully investigate transient states of fast neutron reactors, due to recriticality issues after accident scenarios. The code solves numerical diffusion equation for 1D problem with possible neutron source incorporation. Crank-Nicholson numerical method is used for the transient states. The investigated cases are describing behavior of PWR fuel assembly inside of spent fuel pool and with the incorporated neutron source for better illustration of thermal feedback.https://ojs.cvut.cz/ojs/index.php/APP/article/view/3745 |
| spellingShingle | Filip Osuský Branislav Vrban Peter Ballo Štefan Čerba Jakub Lüley Gabriel Farkas NUMERICAL MULTIGROUP TRANSIENT ANALYSIS OF SLAB NUCLEAR REACTOR WITH THERMAL FEEDBACK Acta Polytechnica CTU Proceedings |
| title | NUMERICAL MULTIGROUP TRANSIENT ANALYSIS OF SLAB NUCLEAR REACTOR WITH THERMAL FEEDBACK |
| title_full | NUMERICAL MULTIGROUP TRANSIENT ANALYSIS OF SLAB NUCLEAR REACTOR WITH THERMAL FEEDBACK |
| title_fullStr | NUMERICAL MULTIGROUP TRANSIENT ANALYSIS OF SLAB NUCLEAR REACTOR WITH THERMAL FEEDBACK |
| title_full_unstemmed | NUMERICAL MULTIGROUP TRANSIENT ANALYSIS OF SLAB NUCLEAR REACTOR WITH THERMAL FEEDBACK |
| title_short | NUMERICAL MULTIGROUP TRANSIENT ANALYSIS OF SLAB NUCLEAR REACTOR WITH THERMAL FEEDBACK |
| title_sort | numerical multigroup transient analysis of slab nuclear reactor with thermal feedback |
| url | https://ojs.cvut.cz/ojs/index.php/APP/article/view/3745 |
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