Transient analysis of a subcritical reactor core with a MOX-Fuel using the birth-and-death model
The operation of the nuclear reactor requires accurate and fast methods and techniques for analysing its kinetics. These techniques become even more important when the MOX-fuel is used due to the lower value of delayed neutron fraction β for 239Pu. Based on a Birth-and-Death process review, the math...
| Main Authors: | , , , |
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| Format: | Article |
| Language: | English |
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Elsevier
2021-06-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573320309384 |
| _version_ | 1818914812500901888 |
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| author | Tamara Korbut Andrei Kuzmin Eduard Rudak Maksim Kravchenko |
| author_facet | Tamara Korbut Andrei Kuzmin Eduard Rudak Maksim Kravchenko |
| author_sort | Tamara Korbut |
| collection | DOAJ |
| description | The operation of the nuclear reactor requires accurate and fast methods and techniques for analysing its kinetics. These techniques become even more important when the MOX-fuel is used due to the lower value of delayed neutron fraction β for 239Pu. Based on a Birth-and-Death process review, the mathematical model of thermal reactor core has been proposed different from existing ones. The analytical method for thermal point-reactor parameters evaluation is described within this work. The proposed method is applied for analysis of the unsteady transient processes taking place in a thermal reactor at its start-up or shutdown power change, as well as during small accidental power variation from the rated value. Theoretical determination of MASURCA reactor core reactivity through the analysis of experimental data on neutron time spectra was made. |
| first_indexed | 2024-12-19T23:52:20Z |
| format | Article |
| id | doaj.art-66705fb75d18435c9b355322d22d2211 |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-12-19T23:52:20Z |
| publishDate | 2021-06-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-66705fb75d18435c9b355322d22d22112022-12-21T20:01:06ZengElsevierNuclear Engineering and Technology1738-57332021-06-0153617311735Transient analysis of a subcritical reactor core with a MOX-Fuel using the birth-and-death modelTamara Korbut0Andrei Kuzmin1Eduard Rudak2Maksim Kravchenko3JIPNR — Sosny, P.O. Box 119, 220109, Minsk, BelarusJIPNR — Sosny, P.O. Box 119, 220109, Minsk, BelarusJIPNR — Sosny, P.O. Box 119, 220109, Minsk, BelarusCorresponding author.; JIPNR — Sosny, P.O. Box 119, 220109, Minsk, BelarusThe operation of the nuclear reactor requires accurate and fast methods and techniques for analysing its kinetics. These techniques become even more important when the MOX-fuel is used due to the lower value of delayed neutron fraction β for 239Pu. Based on a Birth-and-Death process review, the mathematical model of thermal reactor core has been proposed different from existing ones. The analytical method for thermal point-reactor parameters evaluation is described within this work. The proposed method is applied for analysis of the unsteady transient processes taking place in a thermal reactor at its start-up or shutdown power change, as well as during small accidental power variation from the rated value. Theoretical determination of MASURCA reactor core reactivity through the analysis of experimental data on neutron time spectra was made.http://www.sciencedirect.com/science/article/pii/S1738573320309384Nuclear reactor core physicsNeutron kineticsAnalytical calculationsNuclear safety parametersMASURCA subcritical Facility |
| spellingShingle | Tamara Korbut Andrei Kuzmin Eduard Rudak Maksim Kravchenko Transient analysis of a subcritical reactor core with a MOX-Fuel using the birth-and-death model Nuclear Engineering and Technology Nuclear reactor core physics Neutron kinetics Analytical calculations Nuclear safety parameters MASURCA subcritical Facility |
| title | Transient analysis of a subcritical reactor core with a MOX-Fuel using the birth-and-death model |
| title_full | Transient analysis of a subcritical reactor core with a MOX-Fuel using the birth-and-death model |
| title_fullStr | Transient analysis of a subcritical reactor core with a MOX-Fuel using the birth-and-death model |
| title_full_unstemmed | Transient analysis of a subcritical reactor core with a MOX-Fuel using the birth-and-death model |
| title_short | Transient analysis of a subcritical reactor core with a MOX-Fuel using the birth-and-death model |
| title_sort | transient analysis of a subcritical reactor core with a mox fuel using the birth and death model |
| topic | Nuclear reactor core physics Neutron kinetics Analytical calculations Nuclear safety parameters MASURCA subcritical Facility |
| url | http://www.sciencedirect.com/science/article/pii/S1738573320309384 |
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