CALCULATION OF NUCLEAR FUEL CLADDING INTERNAL COATING THICKNESS FOR EMERGENCY RESISTANT NUCLEAR FUEL ELEMENT

IF 0.6 Q4 ENGINEERING, GEOLOGICAL
Hamad Khalifa Hamad Rofida, N. N. Nikitenkov, Viktor N. Kudiyarov
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Abstract

Link for citation: Rofida Hamad Khalifa Hamad, Nikitenkov N.N., Kudiyarov V.N. Calculation of nuclear fuel cladding internal coating thickness for emergency resistant nuclear fuel element. Bulletin of the Tomsk Polytechnic University. Geo Аssets Engineering, 2023, vol. 334, no. 6, рр.27-34. In Rus. The relevance of the study lies in the need to create an emergency resistant fuel for nuclear reactors, based on the study of the consequences of accidents in Chernobyl and Fukushima. The specific problem to which the work is devoted is the creation of thin-film chromium coatings on the inside of nuclear fuel element tubes, which is one of the directions for creating an emergency resistant core of a nuclear reactor. The main aim of the research is to determine the minimum thickness of the chromium coating necessary for adequate protection of the inner side of the fuel rod cladding from nuclear fuel fission fragments. Methods: a well-developed (more than 60 years of improvement) and widely known and recognized software package to simulate the physical processes of radiation and accelerated particle transport in solids using Monte Carlo statistics. The determination of the minimum thickness of the chromium coating to ensure protection of the inner side of the fuel element cladding from the main group of high-energy fission fragments of nuclear fuel was carried out on the basis of calculations using the TRIM program (from the SRIM package). 97Tc, 98Mo, 102Ru, 103Rh, 106Pd, 127I, 133Cs were selected as bombarding the coating from their wide range of nuclear fuel fission fragments, as the most high-energy and at the same time, having different chemical properties. Results. It was found that the minimum thickness of chromium required to provide adequate protection of the inner surface of the fuel tube from the main fission fragments of the U235O2 fuel is 9 µm. Experimental data confirming this result are presented.
应急核燃料元件核燃料包壳内包层厚度计算
引用链接:Rofida Hamad Khalifa Hamad, Nikitenkov n.n., Kudiyarov V.N.耐应急核燃料元件的核燃料包壳内涂层厚度计算。托木斯克理工大学公报。岩土工程Аssets, 2023,第334卷,第2期。6,рр.27-34。俄文。这项研究的相关性在于,需要根据对切尔诺贝利和福岛事故后果的研究,为核反应堆创造一种抗紧急情况的燃料。这项工作的具体问题是在核燃料元件管内部制造薄膜铬涂层,这是制造核反应堆抗紧急堆芯的方向之一。这项研究的主要目的是确定所需的铬涂层的最小厚度,以充分保护燃料棒包壳的内侧免受核燃料裂变碎片的伤害。方法:一个完善的(超过60年的改进)和广泛知名和认可的软件包,模拟辐射和加速粒子输运的物理过程在固体中使用蒙特卡罗统计。在使用TRIM程序(来自SRIM包)进行计算的基础上,确定了铬涂层的最小厚度,以确保燃料元件包层内壁免受核燃料主要高能裂变碎片的保护。选用97Tc、98Mo、102Ru、103Rh、106Pd、127I、133Cs从其广泛的核燃料裂变碎片中轰击涂层,因为它们的能量最高,同时具有不同的化学性质。结果。研究发现,为保护燃料管内表面免受U235O2燃料主要裂变碎片的伤害,所需的最小铬厚度为9µm。给出了验证这一结果的实验数据。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
CiteScore
1.40
自引率
50.00%
发文量
210
审稿时长
5 weeks
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