Assesment of advanced step models for steady state Monte Carlo burnup calculations in application to prismatic HTGR
In this paper, we compare the methodology of different time-step models in the context of Monte Carlo burnup calculations for nuclear reactors. We discuss the differences between staircase step model, slope model, bridge scheme and stochastic implicit Euler method proposed in literature. We focus on...
| Main Authors: | , |
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| Format: | Article |
| Language: | English |
| Published: |
Sciendo
2015-09-01
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| Series: | Nukleonika |
| Subjects: | |
| Online Access: | https://doi.org/10.1515/nuka-2015-0095 |
| _version_ | 1818084384164544512 |
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| author | Kępisty Grzegorz Cetnar Jerzy |
| author_facet | Kępisty Grzegorz Cetnar Jerzy |
| author_sort | Kępisty Grzegorz |
| collection | DOAJ |
| description | In this paper, we compare the methodology of different time-step models in the context of Monte Carlo burnup calculations for nuclear reactors. We discuss the differences between staircase step model, slope model, bridge scheme and stochastic implicit Euler method proposed in literature. We focus on the spatial stability of depletion procedure and put additional emphasis on the problem of normalization of neutron source strength. Considered methodology has been implemented in our continuous energy Monte Carlo burnup code (MCB5). The burnup simulations have been performed using the simplified high temperature gas-cooled reactor (HTGR) system with and without modeling of control rod withdrawal. Useful conclusions have been formulated on the basis of results. |
| first_indexed | 2024-12-10T19:53:02Z |
| format | Article |
| id | doaj.art-7a670d05f41b44cc85c8126134f48029 |
| institution | Directory Open Access Journal |
| issn | 0029-5922 |
| language | English |
| last_indexed | 2024-12-10T19:53:02Z |
| publishDate | 2015-09-01 |
| publisher | Sciendo |
| record_format | Article |
| series | Nukleonika |
| spelling | doaj.art-7a670d05f41b44cc85c8126134f480292022-12-22T01:35:44ZengSciendoNukleonika0029-59222015-09-0160352352910.1515/nuka-2015-0095nuka-2015-0095Assesment of advanced step models for steady state Monte Carlo burnup calculations in application to prismatic HTGRKępisty Grzegorz0Cetnar Jerzy1Department of Nuclear Engineering, Faculty of Energy and Fuels, AGH University of Science and Technology, 30 Mickiewicza Ave., 30-059 Krakow, Poland, Tel.: +48 12 617 2954Department of Nuclear Engineering, Faculty of Energy and Fuels, AGH University of Science and Technology, 30 Mickiewicza Ave., 30-059 Krakow, Poland, Tel.: +48 12 617 2954In this paper, we compare the methodology of different time-step models in the context of Monte Carlo burnup calculations for nuclear reactors. We discuss the differences between staircase step model, slope model, bridge scheme and stochastic implicit Euler method proposed in literature. We focus on the spatial stability of depletion procedure and put additional emphasis on the problem of normalization of neutron source strength. Considered methodology has been implemented in our continuous energy Monte Carlo burnup code (MCB5). The burnup simulations have been performed using the simplified high temperature gas-cooled reactor (HTGR) system with and without modeling of control rod withdrawal. Useful conclusions have been formulated on the basis of results.https://doi.org/10.1515/nuka-2015-0095burnup · high temperature gas-cooled reactor (htgr) · monte carlo · stability · step model |
| spellingShingle | Kępisty Grzegorz Cetnar Jerzy Assesment of advanced step models for steady state Monte Carlo burnup calculations in application to prismatic HTGR Nukleonika burnup · high temperature gas-cooled reactor (htgr) · monte carlo · stability · step model |
| title | Assesment of advanced step models for steady state Monte Carlo burnup calculations in application to prismatic HTGR |
| title_full | Assesment of advanced step models for steady state Monte Carlo burnup calculations in application to prismatic HTGR |
| title_fullStr | Assesment of advanced step models for steady state Monte Carlo burnup calculations in application to prismatic HTGR |
| title_full_unstemmed | Assesment of advanced step models for steady state Monte Carlo burnup calculations in application to prismatic HTGR |
| title_short | Assesment of advanced step models for steady state Monte Carlo burnup calculations in application to prismatic HTGR |
| title_sort | assesment of advanced step models for steady state monte carlo burnup calculations in application to prismatic htgr |
| topic | burnup · high temperature gas-cooled reactor (htgr) · monte carlo · stability · step model |
| url | https://doi.org/10.1515/nuka-2015-0095 |
| work_keys_str_mv | AT kepistygrzegorz assesmentofadvancedstepmodelsforsteadystatemontecarloburnupcalculationsinapplicationtoprismatichtgr AT cetnarjerzy assesmentofadvancedstepmodelsforsteadystatemontecarloburnupcalculationsinapplicationtoprismatichtgr |