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<article article-type="research-article" dtd-version="1.3" xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink" xmlns:xsi="http://www.w3.org/2001/XMLSchema-instance" xml:lang="ru"><front><journal-meta><journal-id journal-id-type="publisher-id">glonucsec</journal-id><journal-title-group><journal-title xml:lang="ru">Глобальная ядерная безопасность</journal-title><trans-title-group xml:lang="en"><trans-title>Global Nuclear Safety</trans-title></trans-title-group></journal-title-group><issn pub-type="ppub">2305-414X</issn><issn pub-type="epub">2499-9733</issn><publisher><publisher-name>National Research Nuclear University "MEPhI"</publisher-name></publisher></journal-meta><article-meta><article-id pub-id-type="doi">10.26583/GNS-2018-02-07</article-id><article-id custom-type="edn" pub-id-type="custom">XHRRBC</article-id><article-id custom-type="elpub" pub-id-type="custom">glonucsec-477</article-id><article-categories><subj-group subj-group-type="heading"><subject>Research Article</subject></subj-group><subj-group subj-group-type="section-heading" xml:lang="ru"><subject>ЭКСПЛУАТАЦИЯ ОБЪЕКТОВ АТОМНОЙ ОТРАСЛИ</subject></subj-group><subj-group subj-group-type="section-heading" xml:lang="en"><subject>OPERATION OF FACILITIES NUCLEAR INDUSTRY</subject></subj-group></article-categories><title-group><article-title>МОДЕЛИРОВАНИЕ ГАММА-СКАНИРУЮЩЕГО ДЕТЕКТОРА С КОЛЛИМАТОРОМ ДЛЯ ИССЛЕДОВАНИЯ ДИФФЕРЕНЦИАЛЬНОГО РАДИОАКТИВНОГО ЗАГРЯЗНЕНИЯ</article-title><trans-title-group xml:lang="en"><trans-title>Modelling of Gamma-Scan Detector with Collimator for Investigating Differential Radioactive Contamination</trans-title></trans-title-group></title-group><contrib-group><contrib contrib-type="author" corresp="yes"><name-alternatives><name name-style="eastern" xml:lang="ru"><surname>Бонах</surname><given-names>А. Э.</given-names></name><name name-style="western" xml:lang="en"><surname>Bonah</surname><given-names>A. E.</given-names></name></name-alternatives><xref ref-type="aff" rid="aff-1"/></contrib><contrib contrib-type="author" corresp="yes"><name-alternatives><name name-style="eastern" xml:lang="ru"><surname>Данейкин</surname><given-names>Ю.</given-names></name><name name-style="western" xml:lang="en"><surname>Daneykin</surname><given-names>Yu.</given-names></name></name-alternatives><xref ref-type="aff" rid="aff-1"/></contrib></contrib-group><aff-alternatives id="aff-1"><aff xml:lang="ru">Томский государственный университет<country>Гана</country></aff><aff xml:lang="en">National Research Tomsk Polytechnic University, Institute of Physics<country>Ghana</country></aff></aff-alternatives><pub-date pub-type="collection"><year>2018</year></pub-date><pub-date pub-type="epub"><day>16</day><month>03</month><year>2026</year></pub-date><volume>0</volume><issue>2</issue><fpage>66</fpage><lpage>73</lpage><permissions><copyright-statement>Copyright &amp;#x00A9; Бонах А.Э., Данейкин Ю., 2026</copyright-statement><copyright-year>2026</copyright-year><copyright-holder xml:lang="ru">Бонах А.Э., Данейкин Ю.</copyright-holder><copyright-holder xml:lang="en">Bonah A.E., Daneykin Y.</copyright-holder><license license-type="creative-commons-attribution" xlink:href="https://creativecommons.org/licenses/by/4.0/" xlink:type="simple"><license-p>This work is licensed under a Creative Commons Attribution 4.0 License.</license-p></license></permissions><self-uri xlink:href="https://glonucsec.elpub.ru/jour/article/view/477">https://glonucsec.elpub.ru/jour/article/view/477</self-uri><abstract><p>В настоящей работе описана разработанная модель радиационного состояния ядерной установки, излагается состав модели, рассмотрены проблемы формирования инженерно-радиационной модели ядерной установки на основе моделирования результатов радиационного контроля и расчетов гамма-излучения в зависимости от состава радионуклидов, активности источников излучения, а также их геометрических размеров и форм. Методы расчета излучения, исходящего от загрязненных узлов элементов ядерной установки, требующих обслуживания или разборки, рассматривают их как источники фотонного излучения, обладающих определенными физическими характеристиками, такими как размеры и активность. Радиоактивные источники рассматриваются как изотропные излучатели. Геометрические размеры и форма таких источников могут быть очень разнообразными. Исследуются существующие методы расчета дозовых полей, создаваемых радионуклидными источниками ионизирующего излучения различных геометрических форм. Обсуждаемые методы основаны на аналогичных подходах и представляют собой математический расчет характеристики поля дозы в зависимости от формы источника, его активности и относительного пространственного расположения расчетной точки в поле и источнике. Поэтому были разработаны специальные методы расчета мощности дозы облучения от протяженных источников.</p></abstract><trans-abstract xml:lang="en"><p>In this paper, a description of the model of the radiation state of a nuclear facility is developed, the composition of the model is outlined, the problems of the formation of the engineering-radiation model of the nuclear facility are considered on the basis of the engineering model of radiation inspection and gamma radiation calculations depending on the radionuclide composition, the activity of radiation sources, and also their geometric sizes and shapes. Methods for calculating radiation emanating from contaminated assemblies of the nuclear facility elements requiring maintenance or disassembly are considered as radionuclide sources of photon radiation having certain physical characteristics, such as dimensions and activity. Sources based on radionuclides are isotropic radiators. The geometric dimensions and shape of such sources can be very diverse in form and size. The existing methods for calculating the dose fields created by radionuclide sources of ionizing radiation of various geometric shapes are investigated. The methods considered are based on similar approaches and represent a mathematical calculation of the characteristics of the dose field depending on the shape of the source, its activity and the relative spatial location of the calculated point in the field and the source. Therefore, special methods for calculating exposure dose rate from extended sources have been developed.</p></trans-abstract><kwd-group xml:lang="ru"><kwd>вывод из эксплуатации</kwd><kwd>радионуклиды</kwd><kwd>канонические</kwd><kwd>моноэнергетические</kwd><kwd>затухание</kwd><kwd>детектор</kwd><kwd>фантом</kwd><kwd>цилиндр</kwd><kwd>дезактивация</kwd><kwd>радиоактивность</kwd><kwd>гамма</kwd></kwd-group><kwd-group xml:lang="en"><kwd>Decommissioning</kwd><kwd>radionuclide</kwd><kwd>canonical</kwd><kwd>monoenergetic</kwd><kwd>attenuation</kwd><kwd>detector</kwd><kwd>phantom</kwd><kwd>cylinder</kwd><kwd>decontaminate</kwd><kwd>radioactivity</kwd><kwd>gamma</kwd></kwd-group></article-meta></front><back><ref-list><title>References</title><ref id="cit1"><label>1</label><citation-alternatives><mixed-citation xml:lang="ru">Agostinelli S. etc. GEANT4–a simulation toolkit. 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