在 FONESYS 活动期间评估 CATHARE 3 代码中的分层和夹带模型

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Sofia Carnevali, Philippe Fillion
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引用次数: 0

摘要

本文介绍了根据在水平 TPTF(两相试验设施)和 Mantilla 设施中进行的试验对 CATHARE 3 代码进行的评估。这项活动属于核反应堆热工水力论坛(FONESYS)的基准测试框架。该基准的目的是突出系统热工水力代码在预测水平分层标准、液滴夹带开始和夹带率方面的能力。日本 JAERI 公司进行的水平 TPTF(TPTF-H)试验的目标之一是分析轻水反应堆水平支腿的热-水力反应。所考虑的试验是在稳态和饱和蒸汽/水两相流动条件下进行的,压力介于 3 兆帕和 12 兆帕之间。CATHARE 代码的模拟结果与 TPTF-H 的实验结果基本吻合,但在分层机制预测等方面仍有改进的必要。Mantilla 在两个不同直径的水平测试断面上进行了低压空气/水实验,实验条件从分层流到环形流,包括液滴夹带。将双流体 6 方程模型和 CATHARE 的 3 场模型得出的夹带分数与实验数据进行了比较。针对夹带和沉积过程,对现有模型提出了一些改进建议,以更好地适应实验。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Assessment of stratification and entrainment models in CATHARE 3 code during FONESYS activities
This paper presents the assessment of CATHARE 3 code against tests performed in the horizontal TPTF (Two Phase Tests Facility) and Mantilla facilities. This activity falls within the framework of a benchmark conducted by the Forum & Network of System Thermal-Hydraulics Codes in Nuclear Reactor Thermal-Hydraulics (FONESYS). The aim of this benchmark is to highlight the capabilities of system thermal–hydraulic codes to predict the horizontal stratification criteria and the onset of droplet entrainment and entrainment rate. One of the objectives of horizontal TPTF (TPTF-H) experiments, conducted by JAERI (Japan), was to analyse the thermal–hydraulic responses in the horizontal legs of Light Water Reactors. The considered tests were at steady state and saturated steam/water two-phase flow conditions for a pressure varying between 3 MPa and 12 MPa. CATHARE code simulations show a general rather good agreement with TPTF-H experimental results although some improvements like the stratification regime prediction seem necessary. In two horizontal test sections with different diameters, Mantilla carried out air/water experiments at low pressure, from stratified to annular flow conditions, including droplet entrainment. Entrainment fraction obtained both with the two-fluid 6-equation model and the 3-field model of CATHARE are compared against the experimental data. Some improvements of the existing models are proposed for the entrainment and deposition processes to better fit the experiments.
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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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