核破冰船和小型核电站反应堆中E110合金燃料棒包壳的腐蚀

IF 0.3 4区工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY

Atomic Energy Pub Date : 2025-07-09 DOI:10.1007/s10512-025-01223-x

G. V. Kulakov, Yu. V. Konovalov, A. V. Vatulin, A. A. Kosaurov, S. A. Ershov, E. V. Maynikov, A. V. Kozlov, V. I. Sorokin, A. M. Savchenko

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引用次数: 0

摘要

E110锆合金广泛应用于运输反应堆，特别是核破冰船堆芯的燃料棒包层。在破冰船核心的条件下，这些覆层的腐蚀倾向于从均匀转变为点蚀。运行和堆后研究表明，E110锆合金包层燃料棒的性能可能由于点蚀的发展而受到限制。本文提供了旨在解释核动力破冰船核心腐蚀机制的假设。

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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Corrosion of fuel rod claddings made of E110 alloy in reactors of nuclear icebreakers and small nuclear power plants

E110 zirconium alloy is widely used as a cladding for fuel rods in the core of transport reactors, in particular, nuclear icebreakers. The corrosion of these claddings in the conditions of the icebreaker core tends to convert from uniform to pitting. Operational and post-reactor studies show that the performance of fuel rods with E110 zirconium alloy claddings may be limited due to the development of pitting corrosion. The paper provides assumptions aimed at explaining corrosion mechanisms in the core of nuclear icebreakers.

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来源期刊

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.