Steam generator model design parameter sensitivity study for small modular reactor system

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-04-15 Epub Date: 2025-03-03 DOI:10.1016/j.nucengdes.2025.113973
Palash K. Bhowmik , Congjian Wang , Nicholas Hernandez , Tejas Kedlaya , Piyush Sabharwall
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Abstract

This study focuses on design parameter sensitivity studies pertaining to several Once-Through Steam Generator (OTSG) model cases both with and without a riser using python and advanced risk assessment and optimization tool, i.e. Risk Analysis Virtual Environment (RAVEN) developed at Idaho National Laboratory (INL), to support a Small Modular Reactor (SMR) system. The presented Steam Generator (SG) python-based model is a mathematical representation of a steam-generating unit for a Pressurized Water Reactor (PWR)-type SMR system, including fluid flow and heat transfer equations, models, and correlations. Design studies involve changing the model’s input design parameters (e.g., temperature, pressure, mass flow rate) to observe the resulting effects on the output of the system, such as the Heat Transfer Coefficient (HTC), Reynolds number, Nusselt number, and heat transfer performance. Sensitivity studies analyze the degree to which system output and/or desired parameters (e.g., HTC or heat transfer performance) are sensitive to changes in the input parameters. By using RAVEN, detailed design parametric sensitivity studies. Six input parameters—namely, the pressure, temperature, and mass flow rate for the inlet of the primary-side (hot fluid) and secondary-side (cold fluid) of the SG—were randomly perturbed via RAVEN’s Monte Carlo Sampler module, using uniform distributions (i.e., ±1%, ±5% and ±10 % relative changes) for 600 samples. The analysis results give valuable insights into SG system performance, and provide justification for further research and development such as optimized sensor placement, design verification, validation, and optimization.
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小型模块化反应堆系统蒸汽发生器模型设计参数敏感性研究
本研究的重点是使用python和先进的风险评估和优化工具,即爱达荷国家实验室(INL)开发的风险分析虚拟环境(RAVEN),对几种有立管和无立管的一次性蒸汽发生器(OTSG)模型进行设计参数敏感性研究,以支持小型模块化反应堆(SMR)系统。提出的蒸汽发生器(SG) python模型是压水堆(PWR)型SMR系统蒸汽发生单元的数学表示,包括流体流动和传热方程、模型和相关性。设计研究涉及改变模型的输入设计参数(如温度、压力、质量流量),以观察由此产生的对系统输出的影响,如传热系数(HTC)、雷诺数、努塞尔数和传热性能。敏感性研究分析系统输出和/或期望参数(如HTC或传热性能)对输入参数变化的敏感程度。利用RAVEN,详细设计参数灵敏度研究。通过RAVEN的蒙特卡罗采样器模块,对600个样品采用均匀分布(即±1%,±5%和±10%的相对变化)随机扰动6个输入参数,即sgs一次侧(热流体)和二次侧(冷流体)进口的压力,温度和质量流量。分析结果为SG系统性能提供了有价值的见解,并为进一步的研究和开发提供了理由,例如优化传感器放置,设计验证,验证和优化。
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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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