Calculation and experimental studies for substantiating the design of BREST-OD-300 reactor sampler

IF 0.4 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY
O. A. Yarmolenko, M. S. Morkin, V. V. Lemekhov, A. Yu. Deryabin, R. N. Lavrenov, A. V. Mikhaylov, A. V. Kolmogortsev
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引用次数: 0

Abstract

The paper considers the development of an innovative lead coolant sampling device for the BREST-OD-300 pilot demonstration fast neutron reactor developed in the Russian Federation within the framework of the Generation IV international initiative. The sampler is equipped with a lateral inclined channel located above the level of the lead coolant and a curved section for sampling both at an operating reactor and in a shutdown mode. The sampler design is protected by two patents of the Russian Federation. The results of tests on loading/unloading a capillary transport tube into a curved sampling channel and the reverse operation are considered. Moreover, the paper presents the results of tests on filling a sampling capsule with a lead coolant sample and its holding during removal from the reactor. The software of the sampler control system was tested for automatic sampling. The performance of the designed sampler is additionally confirmed by thermal engineering, strength, and radiation calculations.

Abstract Image

为验证BREST-OD-300反应器取样器设计而进行的计算和实验研究
本文考虑在第四代国际倡议框架内,为俄罗斯联邦开发的BREST-OD-300中试示范快中子反应堆开发一种创新的铅冷却剂取样装置。采样器配备位于铅冷却剂水平上方的横向倾斜通道和弯曲部分,用于在运行反应堆和关闭模式下进行采样。采样器设计受俄罗斯联邦两项专利保护。考虑了在弯曲取样通道中加载/卸载毛细管输运管和反向操作的试验结果。此外,本文还介绍了用铅冷却剂样品填充采样胶囊及其在从反应器中移除时的保持的测试结果。对采样器控制系统软件进行了自动采样测试。设计的采样器的性能还通过热工、强度和辐射计算进行了验证。
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
Atomic Energy
Atomic Energy 工程技术-核科学技术
CiteScore
1.00
自引率
20.00%
发文量
100
审稿时长
4-8 weeks
期刊介绍: Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.
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