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

• 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
• 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.

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.