Study into the Physical Chemistry and Technology of Alkali Liquid Metal Coolantsn for Nuclear and Thermonuclear Power Plants

A. Sorokin, J. Kuzina, R. Askhadullin, V. V. Alekseev
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引用次数: 1

Abstract

It is shown that, as the result of developing alkali liquid metal coolants, including sodium, eutectic sodium-potassium alloy, lithium and cesium, the scientific basis has been established for their application in nuclear power. The paper presents data from investigations of thermophysical, neutronic and physicochemical properties and characteristics of various alkali liquid metal coolants, the content of solid-phase and dissolved impurities in coolants, mass transport of impurities in circulation circuits with alkali liquid metal coolants, development of systems for removal of impurities, and control of the content of impurities in alkali liquid metal coolants. Alkali liquid metal coolants are considered as a part of a system that includes a structural material in contact with the coolant, and a gas space that compensates for the thermal expansion of the coolant. The state of the system is defined by the physicochemical properties of the system’s components. And the coolant and the structural materials also represent subsystems consisting of a base material, a coolant and impurities contained both in the material and in the coolant. It has been shown that each alkali liquid metal coolant has its own set of impurities that define its technology. It depends on the physicochemical properties of the solution of the structural material impurities and components in the coolant. Objectives have been formulated for investigating further alkali liquid metal coolants, as stemming from the need to improve the efficiency, environmental friendliness, reliability and safety, and for extending the life of nuclear power plants in operation or under design. Alkali liquid metals are promising candidate materials for being used in thermonuclear power not only as the coolant but also as the tritium breeding medium. These include, first of all, lithium and its eutectic alloy with lead (17 at. % of lithium). The possibility for using lithium or a lithium-lead alloy as a coolant in the blanket of the international thermonuclear power reactor is compared.
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核电厂和热核电厂用碱液金属冷却剂的物理化学和工艺研究
结果表明,钠、共晶钠钾合金、锂、铯等碱金属液态冷却剂的研制,为其在核电中的应用奠定了科学基础。本文介绍了各种碱液金属冷却剂的热物理、中子和物理化学性质和特性,冷却剂中固相和溶解杂质的含量,碱液金属冷却剂循环回路中杂质的质量传递,杂质去除系统的开发以及碱液金属冷却剂中杂质含量的控制等方面的研究数据。碱液态金属冷却剂被认为是系统的一部分,该系统包括与冷却剂接触的结构材料和补偿冷却剂热膨胀的气体空间。系统的状态是由系统组成部分的物理化学性质决定的。而冷却剂和结构材料也代表子系统,由基础材料,冷却剂和材料和冷却剂中含有的杂质组成。研究表明,每一种碱金属液态冷却剂都有自己的一套杂质,这些杂质决定了它的技术。它取决于冷却剂中结构材料杂质和成分的溶液的物理化学性质。由于需要提高效率、环境友好性、可靠性和安全性,以及为了延长正在运行或正在设计中的核电站的寿命,已经制定了进一步研究碱液金属冷却剂的目标。碱液金属是热核发电中很有前途的候选材料,不仅可以作为冷却剂,还可以作为氚增殖介质。这些首先包括锂及其与铅(17 at)的共晶合金。%的锂)。比较了在国际热核反应堆包层中使用锂或锂铅合金作为冷却剂的可能性。
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来源期刊
Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika
Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika Energy-Nuclear Energy and Engineering
CiteScore
0.40
自引率
0.00%
发文量
30
期刊介绍: The scientific journal Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika is included in the Scopus database. Publisher country is RU. The main subject areas of published articles are Nuclear Energy and Engineering, Физика, Приборостроение, метрология и информационно-измерительные приборы и системы, Информатика, вычислительная техника и управление, Энергетика. Before sending a scientific article, we recommend you to read the section For authors. This will allow you to prepare an article better for publication, to make it more interesting for the readers and useful for the scientific community. By following these steps, you will greatly increase the likelihood of your scientific article publishing in journals included in international citation systems (e.g., Scopus). Then you may choose a different journal, select the journal included to list of SAC Russia journal list, or send your scientific work for review and publication.
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