Radiation spectroscopy of irradiated VVER-1200 fuel with burnable Am-absorber: A computational approach

IF 1.8 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Applied Radiation and Isotopes Pub Date : 2025-04-01 Epub Date: 2025-01-16 DOI:10.1016/j.apradiso.2025.111674

Sergey V. Bedenko , Gennady N. Vlaskin , Sergey D. Polozkov , Dmitry G. Veretennikov , Alexey S. Demin , Nima Ghal-Eh , Faezeh Rahmani

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Abstract

Safe storage of fresh and irradiated fuel is ensured by solving the problem of photon emission protection. The neutron component is usually not taken into account due to its low intensity. However, for the new VVER-1200 fuel, the neutron component consideration is a mandatory procedure for radiation safety. In this study, the radiation dose was calculated for a fuel consisting of UO₂ with a heterogeneous distribution of Am₂O₂ microcapsules, and the (α, n) component of the neutron background was evaluated. A comparative analysis of radiation characteristics of fuel assemblies shows that there is a significant excess in both the neutron and the photon components of the fuel under study. The yield and dose of neutrons from Am−containing fuel exceed those of uranium−based fuels by a factor of two, and when calculating the dose, it is necessary to take into account the energy spectrum of (α, n) neutrons in Am₂O₂ microcapsules. The analysis of the impact of Am on the photon component indicates that ensuring radiation safety for both fresh and irradiated fuels necessitates addressing challenges associated with photon radiation protection. This study aims to establish comprehensive procedures and guidelines for the handling of novel fuel materials during both production and post-irradiation processes within the reactor environment.

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含可燃am吸收剂辐照VVER-1200燃料的辐射光谱：一种计算方法。

通过解决光子发射防护问题，保证了新鲜辐照燃料的安全储存。中子成分由于强度低，通常不考虑。然而，对于新的VVER-1200燃料，中子成分的考虑是辐射安全的强制性程序。在本研究中，计算了由UO2组成的燃料中Am2O2微胶囊分布不均的辐射剂量，并评估了中子背景的（α, n）分量。对燃料组件辐射特性的比较分析表明，所研究的燃料的中子和光子成分都有明显的过剩。含am燃料的中子产率和剂量是铀基燃料的两倍，在计算剂量时，必须考虑到Am2O2微胶囊中（α, n）中子的能谱。对Am对光子组件影响的分析表明，确保新鲜和辐照燃料的辐射安全需要解决与光子辐射防护相关的挑战。本研究旨在为新型燃料材料在反应堆生产和辐照后处理过程中建立全面的程序和指导方针。

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

Applied Radiation and Isotopes 工程技术-核科学技术

CiteScore

3.00

自引率

12.50%

发文量

406

审稿时长

13.5 months

期刊介绍： Applied Radiation and Isotopes provides a high quality medium for the publication of substantial, original and scientific and technological papers on the development and peaceful application of nuclear, radiation and radionuclide techniques in chemistry, physics, biochemistry, biology, medicine, security, engineering and in the earth, planetary and environmental sciences, all including dosimetry. Nuclear techniques are defined in the broadest sense and both experimental and theoretical papers are welcome. They include the development and use of α- and β-particles, X-rays and γ-rays, neutrons and other nuclear particles and radiations from all sources, including radionuclides, synchrotron sources, cyclotrons and reactors and from the natural environment. The journal aims to publish papers with significance to an international audience, containing substantial novelty and scientific impact. The Editors reserve the rights to reject, with or without external review, papers that do not meet these criteria. Papers dealing with radiation processing, i.e., where radiation is used to bring about a biological, chemical or physical change in a material, should be directed to our sister journal Radiation Physics and Chemistry.