THE EFFICIENCY OF RADIATION SHIELDING MADE FROM MATERIALS WITH HIGH ATOMIC NUMBER AND LOW MASS DENSITY-Reference-Cited by-同舟云学术

THE EFFICIENCY OF RADIATION SHIELDING MADE FROM MATERIALS WITH HIGH ATOMIC NUMBER AND LOW MASS DENSITY

Published:2021-04-07 Issue: Volume: Page:74-79
ISSN:
Container-title:Problems of Atomic Science and Technology
language:
Short-container-title:

Author:

Rudychev V.G.,Azarenkov M.O.,Girka I.O.,Rudychev Y.V.

Abstract

The radiation shielding from γ-quanta of the existing transport containers (TC) for transportation of spent nuclear fuel (SNF) is made of steel or steel plus Pb 25…30 cm thick and weighting ~ 60…80 t. The application of materials with high atomic number, dispersed (solids grinded to a powdery state) to the densities in the range 4 < ρ < 8 g/cm3, is investigated. Simulations based on the Monte Carlo method show that at the densities of dispersed depleted U larger than 5 g/cm3 and shielding thicknesses of more than 30 cm, the absorption of γ-quanta of SNF is greater than that of the shielding made of steel of the same thickness. The application of such materials, while the weight characteristics of the shields are not exceeded, provides radiation shielding for SNF with the high burnup rate and the smaller cooling time or larger amount of the transported SNF.

Publisher

Problems of Atomic Science and Technology

Reference7 articles.

1. A. Historical. Review of the Safe Transport of Spent Nuclear Fuel, FCRD-NFST-2016-000474 (Rev. 1), ORNL, Oak Ridge, 2016, 88 p.

2. Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transportation of Used Fuel – Revision 1, September 30, 2013, Argonne National Laboratory, FCRD-UFD2013-000294б, ANL-13/15.

3. О.В. Григораш, О.М. Дибач, С.М. Кондратьєв и др. Питання ядерної та радіаційної безпеки централізованого сховища відпрацьованого ядерного палива АЕС України // Ядерна та радіаційна безпека. 2017, т. 3(75), с. 3-10.

4. V.G. Rudychev, N.A. Azarenkov, I.O. Girka, Y.V. Rudychev. Efficiency of various materials application for radiation shielding at transportation and storage of spent nuclear fuel by dry method // Problems of Atomic Science and Technology. Series “Physics of Radiation Effect and Radiation Materials Science”. 2020, N 2(126), p. 64-70.

5. В.Г. Рудичев, М.О. Азарєнков, І.О. Гірка, Є.В. Рудичев. Контейнер для транспортування та/або зберігання відпрацьованого ядерного палива. Патент України №145814 від 06.01.2021, Бюл. №1.

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Composite cellulose/bismuth/PVA nanocrystal for high-performance X-ray radiation shielding;Radiation Physics and Chemistry;2025-01

2. Shielding and corrosion properties of the Alloy 709 as canister material for spent nuclear fuel dry casks;Defence Technology;2023-03

3. Optimization of radiation shields made of Fe and Pb for the spent nuclear fuel transport casks;Nuclear Engineering and Technology;2023-02

4. EFFICIENCY OF COMBINED Fe AND Pb RADIATION SHIELD OF TRANSPORT CASKS FOR SNF TRANSPORTATION;Problems of Atomic Science and Technology;2022-09-12