新临界组件堆芯冷却失效时的散热评估

Y. Eguchi, T. Sugawara, K. Nishihara, Y. Tazawa, K. Tsujimoto
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引用次数: 0

摘要

作为长寿命放射性核素嬗变专用系统,日本原子能机构(JAEA)一直在进行加速器驱动亚临界系统(ADS)的研究与开发。为了促进ADS的研发,JAEA b[1]计划在J-PARC项目中建立嬗变物理实验设施(TEF-P)。TEF-P使用的是具有较大衰变热的微量锕系元素(MA)燃料,因此在堆芯冷却系统失效时,堆芯温升的评估非常重要。本研究旨在评估TEF-P堆芯的自然冷却特性,并实现在事故(堆芯冷却系统失效)中不损坏堆芯和燃料的设计。利用模拟装置对空矩形点阵管的传热特性进行了验证。结果表明,空矩形点阵管的实际换热系数约为理论自由对流模型的2.2倍。结果表明,在空矩形点阵管中插入任意块都可以获得较高的换热系数。利用实验结果得到的换热系数,采用三维换热分析方法进行热分析。计算结果表明,堆芯最高温度为294℃,低于设计标准温度327℃。通过研究,提出了堆芯冷却系统失效时堆芯温度低于设计准则的设计条件。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Evaluation of Heat Removal During the Failure of the Core Cooling for New Critical Assembly
The Japan Atomic Energy Agency (JAEA) has been conducting the research and development (R&D) on accelerator-driven subcritical system (ADS) as a dedicated system for the transmutation of long-lived radioactive nuclides. To foster the R&D of ADS, the Transmutation Physics Experimental Facility (TEF-P) in the J-PARC project has been planned to build by JAEA [1]. The TEF-P is used minor actinide (MA) fuel which has large decay heat, so during the failure of the core cooling system, the evaluation of the core temperature increase is important. This study aims to evaluate the natural cooling characteristics of TEF-P core and to achieve a design that does not damage the core and the fuels during an accident (the failure of the core cooling system). The experiments using mockup device was performed to validate the heat transfer characteristics in the empty rectangular lattice tube. It was obtained that the actual heat transfer coefficient of empty rectangular lattice tube was about 2.2 times larger than the theoretical free convection model. It was also confirmed that the insertion of any block into the empty rectangular lattice tube could achieve the higher heat transfer coefficient. Using the heat transfer coefficient obtained by experiment results, thermal analysis was performed by the three-dimensional heat transfer analysis. As a result, the calculation results showed that the maximum core temperature will be 294 °C which is less than the design criterion of temperature, 327 °C. It was presented that the design condition which the core temperature will be below the design criterion during the failure of the core cooling system through this study.
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