Assessment and predicting the axial power distribution effect on the thermal-mechanical parameters of the NuScale nuclear reactor core loaded with TVS-2 M fuel assemblies as well as axial Offset optimizing for load-following operation

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
M.H. Zahedi yeganeh, G.R. Ansarifar, H.Zayermohammadi Rishehri
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Abstract

This study evaluates and examines the thermal–mechanical behavior of a NuScale reactor core which utilizes TVS-2 M hexagonal fuel assemblies. The efficiency of the fuel rods is validated using the FRAPCON code. Initially, the reactor’s core is modeled with the MCNP code to locate the control banks. The design phase ensures the capability to shut down the reactor in two scenarios. In the Hot Zero Power (HZP) scenario, MCNP simulation reveals a sub-critical state with a multiplication factor of 0.94481 ± 0.00023. In the Cold Zero Power (CZP) scenario, the multiplication factor of 0.9935 ± 0.00023 confirms the adequacy of control assemblies. Subsequently, a thermal–mechanical analysis is conducted on the fuel rod over 1330 days, confirming its acceptable design and operational effectiveness in the core. Also, one of the parameters that can be examined during reactor control and load-following operations is Axial Offset (AO). Therefore, the study investigates the impact of AO on fuel rod’s thermal–mechanical changes. The MCNP code was used to simulate control rod inputs and obtain power distribution data for each AO deviation. Based on assessments regarding the association between AO and the thermal–mechanical characteristics of fuel, it has been determined that the impact of power distribution increases significantly over time, particularly towards the end of the operational period. Afterward, based on FRAPCON results, an artificial neural network (ANN) estimator is developed to predict thermal–mechanical parameters at the beginning of the cycle (BOC). The ANN proves to be a powerful method for estimation. By employing the ANN estimator and exploring different cost functions based on thermal–mechanical parameters, the optimal AO is determined using a genetic algorithm, which enhances the reactor’s performance, particularly in load-following operations. The attained optimal AO value for various cost functions are as follows: −0.10316, −0.19635, and −0.25817. This approach allows for the selection of the most efficient AO, leading to improved performance of the NuScale reactor core loaded with TVS-2 M hexagonal fuel assemblies. Indeed, optimization of AO is very important and useful for load-following operation.
评估和预测轴向功率分配对装载tvs - 2m燃料组件的NuScale核反应堆堆芯热力学参数的影响,以及负载跟随运行的轴向偏移优化
本研究对采用tvs - 2m六方燃料组件的NuScale反应堆堆芯的热力学行为进行了评价和检验。使用FRAPCON代码验证燃料棒的效率。最初,用MCNP代码对反应堆堆芯进行建模,以确定控制库的位置。设计阶段确保在两种情况下关闭反应堆的能力。在热零功率(HZP)场景下,MCNP仿真显示亚临界状态,乘法因子为0.94481±0.00023。在冷零功率(CZP)场景中,乘法系数0.9935±0.00023确认控制组件的充分性。随后,对燃料棒进行了1330天的热力学分析,确认了其可接受的设计和在堆芯中的运行有效性。此外,在反应堆控制和负载跟踪操作期间可以检查的参数之一是轴向偏移(AO)。因此,研究了AO对燃料棒热-力学变化的影响。利用MCNP代码模拟控制棒输入,得到各AO偏差下的功率分布数据。根据对AO与燃料的热机械特性之间关系的评估,已确定功率分配的影响随着时间的推移而显著增加,特别是在作业期结束时。然后,基于FRAPCON结果,开发了一种人工神经网络(ANN)估计器来预测周期开始时的热力参数(BOC)。人工神经网络被证明是一种强大的估计方法。通过采用人工神经网络估计器,探索基于热力学参数的不同代价函数,采用遗传算法确定最优AO,提高了反应堆的性能,特别是在负荷跟随操作中。对于各种成本函数,获得的最优AO值如下:−0.10316,−0.19635和−0.25817。这种方法允许选择最有效的AO,从而提高装载tvs - 2m六边形燃料组件的NuScale反应堆堆芯的性能。实际上,AO的优化对于负载跟踪操作非常重要和有用。
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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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