液态金属冷剂快堆设计与安全论证实验设施的综合体

Yu. A. Kuzina, D. Klinov, G. Mikhailov, A. Sorokin, V. Alekseev
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引用次数: 0

摘要

为了证实使用液态金属冷却剂的快堆的安全性和特性,在SSC RF - IPPE建立了一个由20多个不同形状和用途的展台组成的综合体,配备了现代化的测量仪器,包括流体动力、热液压和技术展台。此外,JSC“SSC RF - IPPE”拥有快速物理展台,包括两个关键展台- BFS-1和世界上最大的物理展台BFS-2。本文介绍了为流体力学、传热和冷却剂技术领域的研究而设计的台架的特点和可能性,以支持使用钠、铅和铅铋冷却剂的快堆的运行和计划装置的设备元件和组件的设计解决方案、安全改进和测试,以及用于加速器控制系统和热核融合、空间小功率核电站的台架。-水动力站“SGDI”(空气),“v - 2”(空气),“SGI”(水),“v - 200”(水),“GDK”(空气)。-热液压液态金属支架-“6B”(Na, Na- k),“AR-1”(Na, Na- k),“Pluton”(Na),“SPRUT”(Na, Na- k, Pb, Pb- bi,水)。——技术液态金属站——“Protva-1”(Na)、“Protva-2”(Na)、“PUSHM”(Na)、“Armatura”(Na)、“IK-MT”(Na)、“SID”(Na)、“BTS”(Na)、“TT-1M”(Pb),“TT-2M”(Pb-Bi),“LIS-M”(李)。一个大型钠试验台“SAZ”正在建设中,它可以测试设备的全尺寸原型及其元素,以证实现有和未来的快钠反应堆项目。物理支架的BFS综合体是世界上唯一的各种类型(任何成分,几何形状和配置)核反应堆堆芯全尺寸建模的实验工具。看台的材料和结构可以模拟堆芯、繁殖区、反射器和堆芯内屏蔽,以及燃料循环的元素和乏核燃料和放射性废物的储存设施。基地的反应堆材料(金属钚、氧化物和铀235浓度分别为36%和90%的金属高浓缩铀、数百吨可增殖材料、建筑材料、各种冷却剂)使组装复杂的全尺寸快堆模型和基准实验成为可能,这些实验用于校正中子物理常数和改进计算方法。
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COMPLEX OF EXPERIMENTAL FACILITIES FOR DESIGN AND SAFETY JUSTIFICATION OF FAST REACTORS WITH LIQUID METAL COOLANTS
To substantiate the safety and characteristics of fast reactors with liquid metal coolants, a complex of more than 20 stands of various profiles and purposes, well equipped with modern measuring instruments, including hydrodynamic, thermohydraulic and technological stands, has been created at SSC RF - IPPE. In addition, JSC “SSC RF - IPPE” has a complex of fast physical stands, including two critical stands - BFS-1 and the world's largest physical stand BFS-2. The article presents the characteristics and the possibility of stands designed for research in the field of hydrodynamics, heat transfer and coolant technology in support of design solutions, safety improvement and testing of equipment elements and assemblies of operating and planned installations with fast reactors with sodium, lead and lead-bismuth coolants, as well as for accelerator-controlled systems and thermonuclear fusion, low-power nuclear power plants for space: - Hydrodynamic stands - “SGDI” (air), “V-2” (air), “SGI” (water), “V-200” (water), “GDK” (air). - Thermal-hydraulic liquid metal stands - “6B” (Na, Na-K), “AR-1” (Na, Na-K), “Pluton” (Na), “SPRUT” (Na, Na-K, Pb, Pb-Bi, water). - Technological liquid metal stands - “Protva-1” (Na), “Protva-2” (Na), “PUSHM” (Na), “Armatura” (Na), “IK-MT” (Na), “SID” (Na), “BTS” (Na), “TT-1M” (Pb), “TT-2M” (Pb-Bi), “LIS-M” (Li). A large-scale sodium test stands “SAZ” is under construction, which allows testing full-scale prototypes of equipment and its elements to substantiate existing and future projects of fast sodium reactors. The BFS complex of physical stands is the world's only experimental tool for full-scale modeling of the cores of nuclear reactors of various types (of any composition, geometry and configuration). The materials and construction of the stands allow simulating the core, breeding zones, reflectors and in-core shielding, as well as elements of fuel cycles and storage facilities for spent nuclear fuel and radioactive waste. Reactor materials of the stands (metallic plutonium, oxide and metallic highly enriched uranium with enrichment of 36% and 90% in uranium-235, hundreds of tons of fertile materials, construction materials, various coolants) make it possible to assemble both complex full-scale models of fast reactors, and benchmarks, experiments for which are carried out to correct neutron-physical constants and improve computational methods.
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