Автоматизированная система определения глубины выгорания отработавшего ядерного топлива
The authors analyse their experience in application of semiconductor detectors and development of a breadboard model of the monitoring system for spent nuclear fuel (SNF). Such system should use CdZnTe-detectors in which one-charging gathering conditions are realized. The proposed technique of real...
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| Datum: | 2014 |
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PE "Politekhperiodika", Book and Journal Publishers
2014
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oai:tkea.com.ua:article-3052025-05-30T19:33:29Z Automated system for determining the burnup of spent nuclear fuel Автоматизированная система определения глубины выгорания отработавшего ядерного топлива Mokritskii, V. A. Maslov, O. V. Banzak, O. V. monitoring system burnup nuclear fuel nuclear fuel gamma-ray radiation CdZnTe detector система контроля глубина выгорания ядерное топливо гамма-излучение детектор The authors analyse their experience in application of semiconductor detectors and development of a breadboard model of the monitoring system for spent nuclear fuel (SNF). Such system should use CdZnTe-detectors in which one-charging gathering conditions are realized. The proposed technique of real time SNF control during reloading technological operations is based on the obtained research results. Methods for determining the burn up of spent nuclear fuel based on measuring the characteristics of intrinsic radiation are covered in many papers, but those methods do not usually take into account that the nuclear fuel used during the operation has varying degrees of initial enrichment, or a new kind of fuel may be used. Besides, the known methods often do not fit well into the existing technology of fuel loading operations and are not suitable for operational control. Nuclear fuel monitoring (including burn up determination) system in this research is based on the measurement of the spectrum of natural gamma-radiation of irradiated fuel assemblies (IFA), as from the point of view of minimizing the time spent, the measurement of IFA gamma spectra directly during fuel loading is optimal. It is the overload time that is regulated rather strictly, and burn up control operations should be coordinated with the schedule of the fuel loading. Therefore, the real time working capacity of the system should be chosen as the basic criterion when constructing the structure of such burn up control systems. Анализ опыта авторов в создании системы контроля состояния отработавшего ядерного топлива (ОЯТ), а именно глубины выгорания, начального обогащения и времени выдержки, проведен на основании измерений спектров собственного гамма-излучения ОЯТ. Система базируется на CdZnTe-детекторах, в которых реализованы условия однозарядового сбора. Предложена методика контроля выгорания ОЯТ в реальном времени при проведении технологических операций. PE "Politekhperiodika", Book and Journal Publishers 2014-12-24 Article Article Peer-reviewed Article application/pdf https://www.tkea.com.ua/index.php/journal/article/view/TKEA2014.5-6.63 10.15222/TKEA2014.2.63 Technology and design in electronic equipment; No. 5–6 (2014): Tekhnologiya i konstruirovanie v elektronnoi apparature; 63-71 Технологія та конструювання в електронній апаратурі; № 5–6 (2014): Технология и конструирование в электронной аппаратуре; 63-71 3083-6549 3083-6530 uk https://www.tkea.com.ua/index.php/journal/article/view/TKEA2014.5-6.63/270 Copyright (c) 2014 Mokritskii V. A., Maslov O. V., Banzak O. V. http://creativecommons.org/licenses/by/4.0/ |
| institution |
Technology and design in electronic equipment |
| baseUrl_str |
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| datestamp_date |
2025-05-30T19:33:29Z |
| collection |
OJS |
| language |
Ukrainian |
| topic |
система контроля глубина выгорания ядерное топливо гамма-излучение детектор |
| spellingShingle |
система контроля глубина выгорания ядерное топливо гамма-излучение детектор Mokritskii, V. A. Maslov, O. V. Banzak, O. V. Автоматизированная система определения глубины выгорания отработавшего ядерного топлива |
| topic_facet |
monitoring system burnup nuclear fuel nuclear fuel gamma-ray radiation CdZnTe detector система контроля глубина выгорания ядерное топливо гамма-излучение детектор |
| format |
Article |
| author |
Mokritskii, V. A. Maslov, O. V. Banzak, O. V. |
| author_facet |
Mokritskii, V. A. Maslov, O. V. Banzak, O. V. |
| author_sort |
Mokritskii, V. A. |
| title |
Автоматизированная система определения глубины выгорания отработавшего ядерного топлива |
| title_short |
Автоматизированная система определения глубины выгорания отработавшего ядерного топлива |
| title_full |
Автоматизированная система определения глубины выгорания отработавшего ядерного топлива |
| title_fullStr |
Автоматизированная система определения глубины выгорания отработавшего ядерного топлива |
| title_full_unstemmed |
Автоматизированная система определения глубины выгорания отработавшего ядерного топлива |
| title_sort |
автоматизированная система определения глубины выгорания отработавшего ядерного топлива |
| title_alt |
Automated system for determining the burnup of spent nuclear fuel |
| description |
The authors analyse their experience in application of semiconductor detectors and development of a breadboard model of the monitoring system for spent nuclear fuel (SNF). Such system should use CdZnTe-detectors in which one-charging gathering conditions are realized. The proposed technique of real time SNF control during reloading technological operations is based on the obtained research results. Methods for determining the burn up of spent nuclear fuel based on measuring the characteristics of intrinsic radiation are covered in many papers, but those methods do not usually take into account that the nuclear fuel used during the operation has varying degrees of initial enrichment, or a new kind of fuel may be used. Besides, the known methods often do not fit well into the existing technology of fuel loading operations and are not suitable for operational control. Nuclear fuel monitoring (including burn up determination) system in this research is based on the measurement of the spectrum of natural gamma-radiation of irradiated fuel assemblies (IFA), as from the point of view of minimizing the time spent, the measurement of IFA gamma spectra directly during fuel loading is optimal. It is the overload time that is regulated rather strictly, and burn up control operations should be coordinated with the schedule of the fuel loading. Therefore, the real time working capacity of the system should be chosen as the basic criterion when constructing the structure of such burn up control systems. |
| publisher |
PE "Politekhperiodika", Book and Journal Publishers |
| publishDate |
2014 |
| url |
https://www.tkea.com.ua/index.php/journal/article/view/TKEA2014.5-6.63 |
| work_keys_str_mv |
AT mokritskiiva automatedsystemfordeterminingtheburnupofspentnuclearfuel AT maslovov automatedsystemfordeterminingtheburnupofspentnuclearfuel AT banzakov automatedsystemfordeterminingtheburnupofspentnuclearfuel AT mokritskiiva avtomatizirovannaâsistemaopredeleniâglubinyvygoraniâotrabotavšegoâdernogotopliva AT maslovov avtomatizirovannaâsistemaopredeleniâglubinyvygoraniâotrabotavšegoâdernogotopliva AT banzakov avtomatizirovannaâsistemaopredeleniâglubinyvygoraniâotrabotavšegoâdernogotopliva |
| first_indexed |
2025-09-24T17:30:42Z |
| last_indexed |
2025-09-24T17:30:42Z |
| _version_ |
1850410235853799425 |