Accident Tolerant Materials for LMFR

Author:

Sergeevich Okunev Viacheslav

Abstract

Several concepts of fast reactors with liquid metal coolant (LMFR) are being developed in the world. Lead-cooled reactors are most preferred for the safe nuclear power of the future. Projects of such reactors are being developed in Russia (BREST), the European Union (the latest development is ALFRED), and the USA (a series of STAR low-power reactor designs). The potential capabilities of fuel, coolant, and structural materials considered for use in the core to increase safety have not been exhausted. There are still unused reserves that can significantly increase the self-protection of the reactor. This chapter presents the results of the analysis of the use of new types of nuclear fuel: based on ceramics and beryllium and ceramics and uranium nanopowder. Studies are being conducted on the possibility of optimizing the composition of lead coolant without isotope separation. The possibilities of improving the safety of LMFR with a coolant based on lead extracted from thorium ores are being investigated. The possibility of using tungsten coatings of the cladding of fuel pins deposited using low-temperature plasma spraying is analyzed. The composition of materials was optimized in terms of improving reactor safety. The proposed innovations will significantly increase the self-protection of the reactor from the totality of severe accidents.

Publisher

IntechOpen

Reference53 articles.

1. Kuzmin AM, Okunev VS. Using Variation Methods for Solving Problems of Ensuring and Justifying the Natural Safety of Fast Neutron Reactors. Moscow: MEPhI; 1999. p. 250

2. Okunev VS. Comparative analysis of safety of fast reactors cooled with alloys of liquid metals. News of higher educational institutions. Nuclear Power. 2001;1:57-64

3. Okunev VS. Comprehensive comparative analysis of the use of liquid metals and their alloys for cooling fast reactors. In: Proceedings of Innovate Design and Technologies of Nuclear Power. 3-Ht International Scientific and Technical Conference. Vol. 1. Moscow: JSC “NIKIET” Publ; 2014. pp. 291-302

4. Waltar AE, Reynolds AB. Fast Breeder Reactors. New York, Oxford, Toronto, Sydney, Paris, Frankfurt: PERGAMON PRESS; 1981. p. 853

5. Golden GH et al. Evolution of thermal-hydraulics testing in EBR-II. Nuclear Engineering and Design. 1987;101:3-12. DOI: 10.1016/0029-5493(87) 90145-2

Cited by 3 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

1. One of the preferred concepts of new generation power nuclear reactor;INTERNATIONAL CONFERENCE ON INFORMATICS, TECHNOLOGY, AND ENGINEERING 2021 (InCITE 2021): Leveraging Smart Engineering;2022

2. A systematic approach to minimizing the corrosion rate of structural materials in lead-cooled fast reactors;International Scientific and Practical Symposium "Materials Science and Technology" (MST2021);2022

3. Prospects for the development of the concept of a safe nuclear reactor BREST of maximum limiting power for nuclear energetics of the middle of the XXI century;IOP Conference Series: Materials Science and Engineering;2021-02-01

同舟云学术

1.学者识别学者识别

2.学术分析学术分析

3.人才评估人才评估

"同舟云学术"是以全球学者为主线,采集、加工和组织学术论文而形成的新型学术文献查询和分析系统,可以对全球学者进行文献检索和人才价值评估。用户可以通过关注某些学科领域的顶尖人物而持续追踪该领域的学科进展和研究前沿。经过近期的数据扩容,当前同舟云学术共收录了国内外主流学术期刊6万余种,收集的期刊论文及会议论文总量共计约1.5亿篇,并以每天添加12000余篇中外论文的速度递增。我们也可以为用户提供个性化、定制化的学者数据。欢迎来电咨询!咨询电话:010-8811{复制后删除}0370

www.globalauthorid.com

TOP

Copyright © 2019-2024 北京同舟云网络信息技术有限公司
京公网安备11010802033243号  京ICP备18003416号-3