Experimental study on eutectic reaction between lower head of reactor pressure vessel and molten pool using simulant materials

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2024-12-01 Epub Date: 2024-09-09 DOI:10.1016/j.nucengdes.2024.113584
Zhihong Xiong , Weiqi Cheng , Kaijun Ou , Songbai Cheng , Bing Tan
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Abstract

The eutectic reaction between core materials is an important behavior during reactor severe accidents because it will affect the accident progression. To comprehend the eutectic reaction between molten corium and the lower head of the reactor pressure vessel, this study conducted a series of simulated experiments. Liquid bismuth (Bi) and lead (Pb) rods, chosen for their relatively low eutectic point of 398.5 K, were utilized in a self-designed apparatus. For a more comprehensive understanding, various experimental parameters, including the temperature of Bi pool (548–578 K), temperature of Pb rod (548–578 K), charged gas pressure (0.002–0.006 MPa), weight of load block (3.3–7.3 kg) and style of baffles (type A, type B) were varied. Upon analyzing the experimental observations and quantitative data gathered, we investigated the influence of experimental conditions on the reaction rate. It is found that the temperature of the Bi pool exerts a notably positive influence on the eutectic reaction rate constant, regardless of the baffle pattern and the initial Pb rod temperature, while the role of Pb rod temperature seems to be insignificant. In experiments employing baffle A, both the weight of the load block and gas pressure significantly impact the reaction rate constant. Conversely, in the case of baffle B, their impact is insignificant. Knowledge and evidence gained from this study will be applied to future preparation of high-temperature experiments that involve actual reactor materials. Furthermore, this study furnishes experimental data aimed at enhancing and validating the eutectic reaction related model within the severe accident analysis code for water-cooled reactors.

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利用模拟材料对反应堆压力容器下封头与熔池之间的共晶反应进行实验研究
堆芯材料之间的共晶反应是反应堆严重事故中的一种重要行为,因为它会影响事故的发展。为了理解熔融冕和反应堆压力容器下封头之间的共晶反应,本研究进行了一系列模拟实验。液态铋(Bi)和铅(Pb)棒的共晶点相对较低,为 398.5 K。为了更全面地了解情况,我们改变了各种实验参数,包括铋池温度(548-578 K)、铅棒温度(548-578 K)、充气压力(0.002-0.006 MPa)、负载块重量(3.3-7.3 kg)和挡板样式(A 型、B 型)。通过分析实验观察和收集到的定量数据,我们研究了实验条件对反应速率的影响。结果发现,无论挡板模式和初始铅棒温度如何,铋池温度对共晶反应速率常数都有显著的正向影响,而铅棒温度的作用似乎并不明显。在采用挡板 A 的实验中,负载块重量和气体压力都对反应速率常数有显著影响。相反,在使用挡板 B 的情况下,它们的影响并不明显。本研究获得的知识和证据将用于今后准备涉及实际反应器材料的高温实验。此外,本研究还提供了实验数据,旨在加强和验证水冷反应堆严重事故分析代码中的共晶反应相关模型。
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
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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