Efficiency of various materials application for radiation shielding at transportation and storage of spent nuclear fuel by dry method

Efficiency of various materials application for radiation shielding at transportation and storage of spent nuclear fuel by dry method

A model of the transport container intended for transportation of spent nuclear fuel (SFN) is studied. The passage of γ-quanta from the major long-lived isotopes is examined. The radiation shields made of iron, lead and depleted uranium, which are equivalent in mass to the thickness of iron of 15 to...

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Бібліографічні деталі
Дата:2020
Автори: Rudychev, V.G., Azarenkov, N.A., Girka, I.O., Rudychev, Y.V.
Формат: Стаття
Мова:English
Опубліковано: Національний науковий центр «Харківський фізико-технічний інститут» НАН України 2020
Назва видання:Вопросы атомной науки и техники
Теми:
Problems of modern nuclear power engineering
Онлайн доступ:http://dspace.nbuv.gov.ua/handle/123456789/194365
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Назва журналу:Digital Library of Periodicals of National Academy of Sciences of Ukraine
Цитувати:Efficiency of various materials application for radiation shielding at transportation and storage of spent nuclear fuel by dry method / V.G. Rudychev, N.A. Azarenkov, I.O. Girka, Y.V. Rudychev // Problems of atomic science and tecnology. — 2020. — № 2. — С. 64-70. — Бібліогр.: 10 назв. — англ.

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Digital Library of Periodicals of National Academy of Sciences of Ukraine
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spelling irk-123456789-1943652023-11-23T13:07:19Z Efficiency of various materials application for radiation shielding at transportation and storage of spent nuclear fuel by dry method Rudychev, V.G. Azarenkov, N.A. Girka, I.O. Rudychev, Y.V. Problems of modern nuclear power engineering A model of the transport container intended for transportation of spent nuclear fuel (SFN) is studied. The passage of γ-quanta from the major long-lived isotopes is examined. The radiation shields made of iron, lead and depleted uranium, which are equivalent in mass to the thickness of iron of 15 to 35 cm is considered. The calculations are carried out using the Monte Carlo method (in MCNP and PHITS packages). The change in the characteristics of γ-radiation beyond the shields, made of different materials and with different thicknesses, is determined. For SNF from WWER-1000 with the thicknesses up to ⁓ 21 cm, the shield made of lead and uranium is shown to be more effective. If the thickness of the shield exceeds ⁓ 21 cm, then the shield made of iron is more effective. Increasing the thickness of the shields above 25 cm is shown to be inefficient, since the shields mass increases but the dose rate decreases slightly in this case. У рамках моделі транспортного контейнера для перевезення ВЯП досліджено проходження γ-квантів від основних довгоживучих ізотопів через радіаційні захисти з Fe, Pb і збідненого U, еквівалентних товщині Fe від 15 до 35 см. Виконано розрахунки методом Монте-Карло (у пакетах MCNP і PHITS) випромінювання, що пройшло крізь захисти. Визначено зміну характеристик γ-випромінювання поза захистами з різних матеріалів і товщин. Показано, що для ВЯП ВВЕР-1000 до товщин ⁓ 21 см ефективнішим є захист з Pb і U, а при великих товщинах – захист з Fe. Показано, що не ефективно збільшувати товщини захистів понад 25 см, бо зростає вага захистів, а потужність дози зменшується незначно. В рамках модели транспортного контейнера для перевозки ОЯТ исследовано прохождение γ-квантов от основных долгоживущих изотопов через радиационные защиты из Fe, Pb и обедненного U, эквивалентных толщине Fe от 15 до 35 см. Выполнены расчеты методом Монте-Карло (в пакетах MCNP и PHITS) прошедшего через защиты излучения. Определено изменение характеристик γ-излучения за защитами из разных материалов и толщин. Показано, что для ОЯТ ВВЭР-1000 до толщин ⁓ 21 см более эффективна защита из Pb и U, а при больших толщинах – защита из Fe. Показано, что не эффективно увеличивать толщины защит свыше 25 см, так как растет вес защит, а мощность дозы уменьшается незначительно. 2020 Article Efficiency of various materials application for radiation shielding at transportation and storage of spent nuclear fuel by dry method / V.G. Rudychev, N.A. Azarenkov, I.O. Girka, Y.V. Rudychev // Problems of atomic science and tecnology. — 2020. — № 2. — С. 64-70. — Бібліогр.: 10 назв. — англ. 1562-6016 http://dspace.nbuv.gov.ua/handle/123456789/194365 621.039.546 en Вопросы атомной науки и техники Національний науковий центр «Харківський фізико-технічний інститут» НАН України
institution Digital Library of Periodicals of National Academy of Sciences of Ukraine
collection DSpace DC
language English
topic Problems of modern nuclear power engineering
Problems of modern nuclear power engineering
spellingShingle Problems of modern nuclear power engineering
Problems of modern nuclear power engineering
Rudychev, V.G.
Azarenkov, N.A.
Girka, I.O.
Rudychev, Y.V.
Efficiency of various materials application for radiation shielding at transportation and storage of spent nuclear fuel by dry method
Вопросы атомной науки и техники
description A model of the transport container intended for transportation of spent nuclear fuel (SFN) is studied. The passage of γ-quanta from the major long-lived isotopes is examined. The radiation shields made of iron, lead and depleted uranium, which are equivalent in mass to the thickness of iron of 15 to 35 cm is considered. The calculations are carried out using the Monte Carlo method (in MCNP and PHITS packages). The change in the characteristics of γ-radiation beyond the shields, made of different materials and with different thicknesses, is determined. For SNF from WWER-1000 with the thicknesses up to ⁓ 21 cm, the shield made of lead and uranium is shown to be more effective. If the thickness of the shield exceeds ⁓ 21 cm, then the shield made of iron is more effective. Increasing the thickness of the shields above 25 cm is shown to be inefficient, since the shields mass increases but the dose rate decreases slightly in this case.
format Article
author Rudychev, V.G.
Azarenkov, N.A.
Girka, I.O.
Rudychev, Y.V.
author_facet Rudychev, V.G.
Azarenkov, N.A.
Girka, I.O.
Rudychev, Y.V.
author_sort Rudychev, V.G.
title Efficiency of various materials application for radiation shielding at transportation and storage of spent nuclear fuel by dry method
title_short Efficiency of various materials application for radiation shielding at transportation and storage of spent nuclear fuel by dry method
title_full Efficiency of various materials application for radiation shielding at transportation and storage of spent nuclear fuel by dry method
title_fullStr Efficiency of various materials application for radiation shielding at transportation and storage of spent nuclear fuel by dry method
title_full_unstemmed Efficiency of various materials application for radiation shielding at transportation and storage of spent nuclear fuel by dry method
title_sort efficiency of various materials application for radiation shielding at transportation and storage of spent nuclear fuel by dry method
publisher Національний науковий центр «Харківський фізико-технічний інститут» НАН України
publishDate 2020
topic_facet Problems of modern nuclear power engineering
url http://dspace.nbuv.gov.ua/handle/123456789/194365
citation_txt Efficiency of various materials application for radiation shielding at transportation and storage of spent nuclear fuel by dry method / V.G. Rudychev, N.A. Azarenkov, I.O. Girka, Y.V. Rudychev // Problems of atomic science and tecnology. — 2020. — № 2. — С. 64-70. — Бібліогр.: 10 назв. — англ.
series Вопросы атомной науки и техники
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AT azarenkovna efficiencyofvariousmaterialsapplicationforradiationshieldingattransportationandstorageofspentnuclearfuelbydrymethod
AT girkaio efficiencyofvariousmaterialsapplicationforradiationshieldingattransportationandstorageofspentnuclearfuelbydrymethod
AT rudychevyv efficiencyofvariousmaterialsapplicationforradiationshieldingattransportationandstorageofspentnuclearfuelbydrymethod
first_indexed 2024-03-31T09:11:03Z
last_indexed 2024-03-31T09:11:03Z
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