THE SCHEDULE OF THE NEUTRON FIELDS SPECTROMETRY IN THE SM REACTOR AFTER THE MODERNIZATION

S. Enin, A. Belozerova, V. Pavlov, T. Chernisheva
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Abstract

A program for refining the energy spectra of neutron radiation in the neutron trap, core and reflector of the SM-3 reactor after modernization using the certified equipment and verified methods is presented in the article. The relevance of the article lies in familiarization with the experimental implementation of the methods in order to compare the experimental neutron-physical characteristics of the reactor before and after the last reconstruction. During the program creation, the previous experience of spectrometric measurements was taken into account, as well as experiments were carried out under conditions close to those of spectrometry after reconstruction. The results of the research are necessary for the planning of irradiation experiments and verification of calculation methods for determining the neutron-physical characteristics. The results of the described researches cover most science and technology areas, many aspects of human practice, including healthcare. The authors presented results of accompanying experiments, which made it possible to work out the regulations and features of short-term measurements. The developed and optimized program of neutron spectrometry in the SM-3 reactor channels will allow to obtain reliable information on the density of neutron fluxes for the first time after modernization to verify analytical data and to optimize the use of the SM-3 reactor facility to increase the production of transplutonium elements and radionuclide products.
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sm反应堆现代化后中子场光谱测定的时间表
本文介绍了SM-3反应堆现代化改造后,利用经过认证的设备和验证的方法,对中子阱、堆芯和反射镜中的中子辐射能谱进行精化处理的方案。本文的意义在于熟悉这些方法的实验实施,以便比较上次重建前后反应堆的实验中子物理特性。在程序创建过程中,考虑了以往光谱测量的经验,并在重建后接近光谱测量的条件下进行了实验。研究结果对辐照实验的规划和确定中子物理特性的计算方法的验证是必要的。所描述的研究结果涵盖了大多数科学和技术领域,人类实践的许多方面,包括医疗保健。作者提出了相应的实验结果,从而使短期测量的规律和特点得以阐明。在SM-3反应堆通道中开发和优化的中子能谱法方案将使我们能够在现代化后首次获得关于中子通量密度的可靠信息,以验证分析数据,并优化SM-3反应堆设施的使用,以增加跨钚元素和放射性核素产品的生产。
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POSSIBILITY OF APPLICATION OF ZrO2-MgO-CaO CRUCIBLES FOR PRODUCING ALLOY U-10 % Zr CALCULATION ESTIMATION OF THE REQUIRED HEAT GENERATION IN TESTING FUEL ELEMENTS TO ACHIEVE SUPERCRITICAL PARAMETERS OF THE COOLANT UNDER IRRADIATION IN THE RESEARCH NUCLEAR REACTOR FEATURES OF THERMAL HYDRAULICS OF ACTIVE ZONES OF FAST LOW-POWER AND HIGH-POWER SODIUM PRODUCTION REACTORS FOR A CLOSED FUEL CYCLE SYSTEM CALCULATION OF THE STRUCTURAL MATERIALS ACTIVATION BY A FUSION NEUTRON FLUX WITH BPSD CODE HEAT PIPES IN NUCLEAR ENGINEERING
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