Investigation of<sup>244</sup>Cm dynamics production in a WWER-1200 reactor for fuel based on<sup>235</sup>U and MOX fuel
244Cm is a very important nuclide due to the high specific heat release and it may become reasonable to recycle the spent nuclear fuel to extract this isotope. In this work, the dynamics of 244Cm isotope production for the fuel assembly of the WWER-1200 reactor with an enrichment of 4.95% and burnup...
| Main Authors: | , , , , , |
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| Format: | Article |
| Language: | English |
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L.N. Gumilyov Eurasian National University
2021-11-01
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| Series: | Eurasian Journal of Physics and Functional Materials |
| Subjects: | |
| Online Access: | https://www.ephys.kz/jour/article/view/29 |
| _version_ | 1819174604508233728 |
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| author | A. M. Petrovski K. I. Usheva T. N. Korbut E. A. Rudak M. O. Kravchenko L. F. Babichev |
| author_facet | A. M. Petrovski K. I. Usheva T. N. Korbut E. A. Rudak M. O. Kravchenko L. F. Babichev |
| author_sort | A. M. Petrovski |
| collection | DOAJ |
| description | 244Cm is a very important nuclide due to the high specific heat release and it may become reasonable to recycle the spent nuclear fuel to extract this isotope. In this work, the dynamics of 244Cm isotope production for the fuel assembly of the WWER-1200 reactor with an enrichment of 4.95% and burnup up to 70 MW · day/kg was calculated using Serpent Monte Carlo code. A similar calculations was performed for MOX-based fuel assembly with the same irradiation characteristics. It has been shown that production of 244Cm in high burnup uranium dioxide fuel, and especially in MOX fuel, reaches a high value, which can cause problems during spent fuel management. The main problems associated with the curium relates to the residual heat and neutron activity. |
| first_indexed | 2024-12-22T20:41:37Z |
| format | Article |
| id | doaj.art-0f52e0578e9d42038c4a1fe4e7e6f371 |
| institution | Directory Open Access Journal |
| issn | 2522-9869 2616-8537 |
| language | English |
| last_indexed | 2024-12-22T20:41:37Z |
| publishDate | 2021-11-01 |
| publisher | L.N. Gumilyov Eurasian National University |
| record_format | Article |
| series | Eurasian Journal of Physics and Functional Materials |
| spelling | doaj.art-0f52e0578e9d42038c4a1fe4e7e6f3712022-12-21T18:13:19ZengL.N. Gumilyov Eurasian National UniversityEurasian Journal of Physics and Functional Materials2522-98692616-85372021-11-014161210.29317/ejpfm.202004010128Investigation of<sup>244</sup>Cm dynamics production in a WWER-1200 reactor for fuel based on<sup>235</sup>U and MOX fuelA. M. Petrovski0K. I. Usheva1T. N. Korbut2E. A. Rudak3M. O. Kravchenko4L. F. Babichev5State Scientific Institution "The Joint Institute for Power and Nuclear Research -Sosny"Institute for Nuclear Problems of Belarusian State UniversityState Scientific Institution "The Joint Institute for Power and Nuclear Research -Sosny"State Scientific Institution "The Joint Institute for Power and Nuclear Research -Sosny"State Scientific Institution "The Joint Institute for Power and Nuclear Research -Sosny"State Scientific Institution "The Joint Institute for Power and Nuclear Research -Sosny"244Cm is a very important nuclide due to the high specific heat release and it may become reasonable to recycle the spent nuclear fuel to extract this isotope. In this work, the dynamics of 244Cm isotope production for the fuel assembly of the WWER-1200 reactor with an enrichment of 4.95% and burnup up to 70 MW · day/kg was calculated using Serpent Monte Carlo code. A similar calculations was performed for MOX-based fuel assembly with the same irradiation characteristics. It has been shown that production of 244Cm in high burnup uranium dioxide fuel, and especially in MOX fuel, reaches a high value, which can cause problems during spent fuel management. The main problems associated with the curium relates to the residual heat and neutron activity.https://www.ephys.kz/jour/article/view/29curium-244spent fuelwwer-type ractorshigh burnupresidual heat |
| spellingShingle | A. M. Petrovski K. I. Usheva T. N. Korbut E. A. Rudak M. O. Kravchenko L. F. Babichev Investigation of<sup>244</sup>Cm dynamics production in a WWER-1200 reactor for fuel based on<sup>235</sup>U and MOX fuel Eurasian Journal of Physics and Functional Materials curium-244 spent fuel wwer-type ractors high burnup residual heat |
| title | Investigation of<sup>244</sup>Cm dynamics production in a WWER-1200 reactor for fuel based on<sup>235</sup>U and MOX fuel |
| title_full | Investigation of<sup>244</sup>Cm dynamics production in a WWER-1200 reactor for fuel based on<sup>235</sup>U and MOX fuel |
| title_fullStr | Investigation of<sup>244</sup>Cm dynamics production in a WWER-1200 reactor for fuel based on<sup>235</sup>U and MOX fuel |
| title_full_unstemmed | Investigation of<sup>244</sup>Cm dynamics production in a WWER-1200 reactor for fuel based on<sup>235</sup>U and MOX fuel |
| title_short | Investigation of<sup>244</sup>Cm dynamics production in a WWER-1200 reactor for fuel based on<sup>235</sup>U and MOX fuel |
| title_sort | investigation of sup 244 sup cm dynamics production in a wwer 1200 reactor for fuel based on sup 235 sup u and mox fuel |
| topic | curium-244 spent fuel wwer-type ractors high burnup residual heat |
| url | https://www.ephys.kz/jour/article/view/29 |
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