Conceptual approaches and methods of treating the irradiated potential nuclear fuel
Various types of reactors are applied in the world nuclear power industry. One of the ways to implement the existing trend to increase the effectiveness of using nuclear fuel in nuclear power engineering is the growth of its burn-up fraction. The relevance of the research is caused by the problem re...
| Main Authors: | , , , |
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| Format: | Article |
| Language: | Russian |
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Tomsk Polytechnic University
2019-05-01
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| Series: | Известия Томского политехнического университета: Инжиниринг георесурсов |
| Subjects: | |
| Online Access: | http://izvestiya-tpu.ru/archive/article/view/1562 |
| _version_ | 1797812497982423040 |
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| author | Sergey Bedenko Vladimir Knyshev Mikhail Yakovlev Maria Plevaka |
| author_facet | Sergey Bedenko Vladimir Knyshev Mikhail Yakovlev Maria Plevaka |
| author_sort | Sergey Bedenko |
| collection | DOAJ |
| description | Various types of reactors are applied in the world nuclear power industry. One of the ways to implement the existing trend to increase the effectiveness of using nuclear fuel in nuclear power engineering is the growth of its burn-up fraction. The relevance of the research is caused by the problem related to increase of burn-up fraction depth both of normal nuclear fuel and new types of fuel, as well as by the necessity to develop the conceptually new approaches to handling such fuel in storage systems and transport means. The main aim of the research is to optimize the system parameters and schemes of handling in «dry» storage of spent fuel irradiated in uranium-graphite reactor of channel type. The methods. The research and numerical experiments were carried out with the assistance of verified computer codes programs based on the Monte Carlo method (MCU5TPU and Scale5), modern evaluated nuclear data library (ENDF/B-VIII, JENDL-3.3, JEFF 3.0, EXFOR, ROSFOND) and multi-group approximation. The sharing of the precise calculation program code of MCU and Scale allowed carrying out the verification of the obtained results of numerical experiments. The results. The authors have carried out the computational studies of the neutron-physical characteristics of the system of «dry» storage of spent nuclear fuel irradiated in the uranium-graphite reactor. Practical recommendations for optimizing the system parameters and schemes of handling and placement of spent fuel in a «dry» storage were developed. The system parameters and handling schemes in the process of «dry» storage of spent fuel optimized due to the alternating layers of placing fuel with different burn-up and enrichment. multiplying system |
| first_indexed | 2024-03-13T07:39:23Z |
| format | Article |
| id | doaj.art-1fd93cdbd493494c82ccf28b90417b79 |
| institution | Directory Open Access Journal |
| issn | 2500-1019 2413-1830 |
| language | Russian |
| last_indexed | 2024-03-13T07:39:23Z |
| publishDate | 2019-05-01 |
| publisher | Tomsk Polytechnic University |
| record_format | Article |
| series | Известия Томского политехнического университета: Инжиниринг георесурсов |
| spelling | doaj.art-1fd93cdbd493494c82ccf28b90417b792023-06-03T21:06:45ZrusTomsk Polytechnic UniversityИзвестия Томского политехнического университета: Инжиниринг георесурсов2500-10192413-18302019-05-013264Conceptual approaches and methods of treating the irradiated potential nuclear fuelSergey BedenkoVladimir KnyshevMikhail YakovlevMaria PlevakaVarious types of reactors are applied in the world nuclear power industry. One of the ways to implement the existing trend to increase the effectiveness of using nuclear fuel in nuclear power engineering is the growth of its burn-up fraction. The relevance of the research is caused by the problem related to increase of burn-up fraction depth both of normal nuclear fuel and new types of fuel, as well as by the necessity to develop the conceptually new approaches to handling such fuel in storage systems and transport means. The main aim of the research is to optimize the system parameters and schemes of handling in «dry» storage of spent fuel irradiated in uranium-graphite reactor of channel type. The methods. The research and numerical experiments were carried out with the assistance of verified computer codes programs based on the Monte Carlo method (MCU5TPU and Scale5), modern evaluated nuclear data library (ENDF/B-VIII, JENDL-3.3, JEFF 3.0, EXFOR, ROSFOND) and multi-group approximation. The sharing of the precise calculation program code of MCU and Scale allowed carrying out the verification of the obtained results of numerical experiments. The results. The authors have carried out the computational studies of the neutron-physical characteristics of the system of «dry» storage of spent nuclear fuel irradiated in the uranium-graphite reactor. Practical recommendations for optimizing the system parameters and schemes of handling and placement of spent fuel in a «dry» storage were developed. The system parameters and handling schemes in the process of «dry» storage of spent fuel optimized due to the alternating layers of placing fuel with different burn-up and enrichment. multiplying systemhttp://izvestiya-tpu.ru/archive/article/view/1562«dry» storage systemspent nuclear fueleffective neutron multiplication factorburn-up fraction |
| spellingShingle | Sergey Bedenko Vladimir Knyshev Mikhail Yakovlev Maria Plevaka Conceptual approaches and methods of treating the irradiated potential nuclear fuel Известия Томского политехнического университета: Инжиниринг георесурсов «dry» storage system spent nuclear fuel effective neutron multiplication factor burn-up fraction |
| title | Conceptual approaches and methods of treating the irradiated potential nuclear fuel |
| title_full | Conceptual approaches and methods of treating the irradiated potential nuclear fuel |
| title_fullStr | Conceptual approaches and methods of treating the irradiated potential nuclear fuel |
| title_full_unstemmed | Conceptual approaches and methods of treating the irradiated potential nuclear fuel |
| title_short | Conceptual approaches and methods of treating the irradiated potential nuclear fuel |
| title_sort | conceptual approaches and methods of treating the irradiated potential nuclear fuel |
| topic | «dry» storage system spent nuclear fuel effective neutron multiplication factor burn-up fraction |
| url | http://izvestiya-tpu.ru/archive/article/view/1562 |
| work_keys_str_mv | AT sergeybedenko conceptualapproachesandmethodsoftreatingtheirradiatedpotentialnuclearfuel AT vladimirknyshev conceptualapproachesandmethodsoftreatingtheirradiatedpotentialnuclearfuel AT mikhailyakovlev conceptualapproachesandmethodsoftreatingtheirradiatedpotentialnuclearfuel AT mariaplevaka conceptualapproachesandmethodsoftreatingtheirradiatedpotentialnuclearfuel |