A Study on Sodium–Concrete Reaction in Presence of Internal Heating

Author:

Kawaguchi Munemichi1,Miyahara Shinya2,Uno Masayoshi2

Affiliation:

1. Containment Safety Technology Development Group, Fast Reactor Fundamental Technology Development Department, Japan Atomic Energy Agency, 1 Shiraki, Tsuruga-shi, Fukui-ken 919-1279, Japan

2. Research Institute of Nuclear Engineering, University of Fukui, 1-3-33, Kanawa-cho, Tsuruga-shi, Fukui-ken 914-0055, Japan

Abstract

Abstract The sodium–concrete reaction (SCR) is an important phenomenon during severe accidents in sodium-cooled fast reactors (SFRs), as it generates large volumes of hydrogen and aerosols in the containment vessel along with structural concrete ablation. In this study, the chemical reaction beneath the internal heater (800 °C) was investigated in SCR experiments with internal heating. The experiments simulate the effects of obstacles and heating on the SCR. Especially, we focused on the concrete ablation phenomenon because the hydrogen generation is sourced from the moisture in the concrete. The effects of internal heating on the self-termination mechanism are also discussed. The internal heater on the concrete hindered the transport of sodium (Na) into the concrete. Therefore, the reaction between Na and the concrete began at the periphery of the internal heater, where the concrete ablation depth was larger than under the internal heater. The high Na pool temperature (800 °C) largely increased the Na aerosol-release rate, which was explained by Na evaporation and formed a porous reaction-product layer. The Si mass balance and image mapping by an electron-probe micro-analyzer yielded consistent porosities in the reaction-product layer (0.54–0.59). The porous reaction products suppressed the amount of Na transported into the reaction front. Regardless of the internal heater placement, the Na concentration around the reaction front was limited to around 30 wt %. The Na concentration condition was dominantly responsible for the self-termination of the internally heated SCR.

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Reference21 articles.

1. Feedback From Practical Experience With Large Sodium Fire Accidents,1996

2. Sodium Fast Reactor Safety and Licensing Research Plan—Volume I,2012

3. Core-Concrete Interactions Using Molten Steel With Zirconium on a Basaltic Basemat: The SURC-4 Experiment,1989

4. OECD MCCI Project 2-D Core Concrete Interaction (CCI) Tests: Final Report,2006

5. Exploratory Study of Molten Core Material/Concrete Interactions,1978

Cited by 1 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

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