Dynamic modeling and simulation of the GAMA-AHR

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Andang Widi Harto, Kusnanto, Alexander Agung, Diva Jati Kanaya, M. Yayan Adi Putra
{"title":"Dynamic modeling and simulation of the GAMA-AHR","authors":"Andang Widi Harto,&nbsp;Kusnanto,&nbsp;Alexander Agung,&nbsp;Diva Jati Kanaya,&nbsp;M. Yayan Adi Putra","doi":"10.1016/j.nucengdes.2025.114085","DOIUrl":null,"url":null,"abstract":"<div><div>The GAMA-AHR is an aqueous fueled nuclear reactor designed to produce 2000 six-day Ci per week of <sup>99</sup>Mo at thermal power of 200 kW. In this study, the dynamic behavior of the GAMA-AHR was demonstrated. A point reactor dynamics model consisting of point kinetics, heat balance, and reactivity feedback equations was developed to represent the primary system of the GAMA-AHR This reactor dynamics model was implemented in C++, and solved numerically with adaptive Runge Kutta method. Numerical simulation to show the reactor’s steady state and transient behavior is reported in this paper. The transient conditions were simulated for the detection of perturbations caused by a reactivity contribution from the reactivity control system and a reduction in the secondary cooling system’s performance. The model was validated by steady-state simulation at 100 % power, and the results agreed well with previous research and therefore demonstrated its suitability for predicting the reactor’s dynamic behavior. The simulation results showed that reactor power decreased with increasing temperature and decreasing heat transfer capability. It was able to safely operate (without fuel boiling) at 90 % reduced heat transfer capability and power lower than 100 kWh. The simulation results also showed that reactor power can be controlled by adjusting the control rod insertion or the fuel level and the reactor can be independently shut down by the full insertion of the control rod or by full draining of fuel into the fuel drain tank. Thus, the temperature reactivity feedback characteristic and reactivity control systems ensures the inherent safety of the GAMA-AHR.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"438 ","pages":"Article 114085"},"PeriodicalIF":1.9000,"publicationDate":"2025-04-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549325002626","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0

Abstract

The GAMA-AHR is an aqueous fueled nuclear reactor designed to produce 2000 six-day Ci per week of 99Mo at thermal power of 200 kW. In this study, the dynamic behavior of the GAMA-AHR was demonstrated. A point reactor dynamics model consisting of point kinetics, heat balance, and reactivity feedback equations was developed to represent the primary system of the GAMA-AHR This reactor dynamics model was implemented in C++, and solved numerically with adaptive Runge Kutta method. Numerical simulation to show the reactor’s steady state and transient behavior is reported in this paper. The transient conditions were simulated for the detection of perturbations caused by a reactivity contribution from the reactivity control system and a reduction in the secondary cooling system’s performance. The model was validated by steady-state simulation at 100 % power, and the results agreed well with previous research and therefore demonstrated its suitability for predicting the reactor’s dynamic behavior. The simulation results showed that reactor power decreased with increasing temperature and decreasing heat transfer capability. It was able to safely operate (without fuel boiling) at 90 % reduced heat transfer capability and power lower than 100 kWh. The simulation results also showed that reactor power can be controlled by adjusting the control rod insertion or the fuel level and the reactor can be independently shut down by the full insertion of the control rod or by full draining of fuel into the fuel drain tank. Thus, the temperature reactivity feedback characteristic and reactivity control systems ensures the inherent safety of the GAMA-AHR.
GAMA-AHR 的动态建模和模拟
GAMA-AHR是一种水燃料核反应堆,设计用于在200千瓦的热功率下每周产生2000个99Mo的6天Ci。在本研究中,证实了GAMA-AHR的动力学行为。建立了一个由点动力学方程、热平衡方程和反应性反馈方程组成的点反应器动力学模型来表示伽玛- ahr的主系统。该模型采用c++语言实现,采用自适应龙格库塔法进行数值求解。本文对反应器的稳态和瞬态特性进行了数值模拟。为了检测由反应性控制系统的反应性贡献和二冷却系统性能降低引起的扰动,对瞬态条件进行了模拟。该模型在100%功率下进行了稳态仿真验证,结果与前人的研究结果吻合较好,证明了该模型对反应器动态特性的预测适用性。模拟结果表明,反应器功率随温度的升高和传热能力的降低而降低。它能够安全运行(没有燃料沸腾),传热能力降低90%,功率低于100千瓦时。仿真结果还表明,可以通过调节控制棒插入量或燃料位来控制反应堆功率,可以通过控制棒插入量完全或将燃料完全排入燃料漏油箱来实现反应堆的独立停机。因此,温度反应性反馈特性和反应性控制系统保证了GAMA-AHR的固有安全性。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
求助全文
约1分钟内获得全文 求助全文
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.
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术官方微信