摘要：
The helical-coiled once-through steam generator (H-OTSG) has the advantages of compact structure and strong heat transfer ability, and is appropriate for lead-cooled fast reactor. The two-phase flow instability may cause mechanical vibration and thermal fatigue of heat transfer tube bundles, posing a serious threat to the safe operation of the H-OTSG. In this work, the secondary side of the H-OTSG characterized as multi-parallel channels is modeled by RELAP5/MOD3.4 code, and the oscillation behavior during start-up and the influence of structural and operating parameters on system stability are studied based on time-domain method. The results indicate that the pressure, flow rate, and temperature of the secondary fluid exhibit density wave oscillations at the heating section in a (n-2,2) pattern. In addition, increasing inlet throttling, reducing outlet throttling, controlling subcooling within an appropriate range and avoiding operation under low loads are all beneficial for improving the system stability of the helical-coiled once-through steam generator.
期刊：
Hedongli Gongcheng/Nuclear Power Engineering,2023年44(4):49-54 ISSN：0258-0926
作者机构：
School of Nuclear Science and Technology, University of South China, Hunan, Hengyang, 421001, China;Hunan Engineering & Technology Research Center for Virtual Nuclear Reactor, Hunan, Hengyang, 421001, China;Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
摘要：
Space nuclear power reactors have the advantages of small size, long service lives and high-power densities. As these characteristics, space nuclear power reactors can meet the high-power demands of spacecraft. To safely and reliably perform tasks in space with a space nuclear reactor, the control technology of the space nuclear reactor is significant. To study the core power control of a space nuclear reactor, a nonlinear model for the TOPAZ-II core is established by the lumped parameter method and principle of point reactor modeling. Then, directly based on the core nonlinear model, a fuzzy-PID controller is used to control the core power. Finally, the core power control system is built, and dynamic simulations are carried out with multiple transient conditions. The results show that the fuzzy-PID controller can realize core power control well, and its control effect is better than that of PID controller.
作者机构：
[徐士坤; 于涛; 谢金森; 刘金聚] School of Nuclear Science and Technology, University of South China, Hengyang;421001, China;Hunan Engineering & Technology Research Center for Virtual Nuclear Reactor, University of South China, Hengyang;[徐士坤; 于涛; 谢金森; 刘金聚] 421001, China <&wdkj&> Hunan Engineering & Technology Research Center for Virtual Nuclear Reactor, University of South China, Hengyang;[徐士坤; 于涛; 谢金森; 刘金聚] 421001, China
作者机构：
[姜庆丰; Zeng, Wenjie; 于涛; 谢金森; 陈乐至] School of Nuclear Science and Technology, University of South China, Hengyang;Hunan;421001, China;[姜庆丰; Zeng, Wenjie; 于涛; 谢金森; 陈乐至] Hunan;[姜庆丰; Zeng, Wenjie; 于涛; 谢金森; 陈乐至] 421001, China
作者机构：
[于涛; 刘金聚; 谢金森; 谢芹; 陈珍平; 赵鹏程; 刘紫静; Zeng, Wenjie; 徐士坤] School of Nuclear Science and Technology, University of South China, Hengyang;Hunan;421001, China;Hunan Engineering andTechnology Research Center for Virtual Nuclear Reactor, University of South China, Hengyang;[于涛; 刘金聚; 谢金森; 谢芹; 陈珍平; 赵鹏程; 刘紫静; Zeng, Wenjie; 徐士坤] Hunan
摘要：
不同可燃毒物的布置方式可以控制整个燃耗寿期下的反应性波动并且可以提高燃耗深度.本工作在不同富集度下分析可燃毒物的布置方式对堆芯反应性的影响.并对堆芯kef在整个燃耗寿期下的变化趋势进行分析.结果表明:1)含可燃毒物B和Gd的堆芯,采用16根可燃毒物棒的布置方式;含可燃毒物Er和Eu的堆芯,采用28根可燃毒物棒的布置方式;含可燃毒物231 P a、240 P u和241 Am的堆芯,采用组件燃料棒中均含可燃毒物的布置方式.2)在14％富集度下选用240 P u作为可燃毒物;在40％、70％和97％富集度下选用B作为可燃毒物.
期刊：
Progress in Nuclear Energy,2020年121:103214 ISSN：0149-1970
通讯作者：
Yu, Tao
作者机构：
[Jiang, Qingfeng; Zeng, Wenjie; Xie, Jinsen; Yu, Tao] Univ South China, Dept Nucl Sci & Technol, Hengyang City 421001, Peoples R China.
通讯机构：
[Yu, Tao] U;Univ South China, Dept Nucl Sci & Technol, Hengyang City 421001, Peoples R China.
关键词：
Core outlet fuel temperature;Liquid molten salt reactor;Fuzzy PID controller;Load following operation
摘要：
As the molten salt fuel flows in the primary loop system of Liquid Molten Salt Reactor (LMSR), the core outlet fuel temperature can effectively characterize the core operation state. In this paper, a control strategy of the core outlet fuel temperature is designed based on the load power required. First, a nonlinear model of LMSR core is built by the lumped parameter method. Then, according to the relationship between the core outlet fuel temperature and the load power required, the control strategy of LMSR core outlet fuel temperature is established. The PID controller and the fuzzy PID controller are respectively used to design the core outlet fuel temperature control system. The simulation system is directly established by using the core nonlinear model. The simulation of LMSR core load following is carried out. The results show that the core outlet fuel temperature can be controlled well by using either PID controller or fuzzy PID controller.
作者机构：
[陈珍平; 于涛; 张震宇; 马辉强; 谢金森] School of Nuclear Science and Technology, University of South China, Hengyang;421001, China;[郭倩] School of Resource Environment and Safety Engineering, University of South China, Hengyang;Hunan Engineering and Technology Research Center for Virtual Nuclear Reactor, Hengyang;[陈珍平; 郭倩; 于涛; 张震宇; 马辉强; 谢金森] 421001, China<&wdkj&>Hunan Engineering and Technology Research Center for Virtual Nuclear Reactor, Hengyang
通讯机构：
School of Resource Environment and Safety Engineering, University of South China, Hengyang, China
作者机构：
[Zeng, Wenjie; 朱伟聪; 谢金森; 姜庆丰; 于涛] School of Nuclear Science and Technology, University of South China, Hengyang;421001, China;[Zeng, Wenjie; 朱伟聪; 谢金森; 姜庆丰; 于涛] 421001, China
通讯机构：
School of Nuclear Science and Technology, University of South China, Hengyang, China
作者机构：
[周剑东; 谢金森; Zeng, Wenjie; 于涛; 陈珍平; 赵鹏程; 谢芹; 刘紫静] School of Nuclear Science and Technology, University of South China, Hengyang;421001, China;[谢超] Hunan Engineering & Technology Research Center for Virtual Nuclear Reactor, Hengyang;[周剑东; 谢金森; Zeng, Wenjie; 于涛; 陈珍平; 赵鹏程; 谢芹; 刘紫静] 421001, China <&wdkj&> Hunan Engineering & Technology Research Center for Virtual Nuclear Reactor, Hengyang;[周剑东; 谢金森; Zeng, Wenjie; 于涛; 陈珍平; 赵鹏程; 谢芹; 刘紫静; 谢超] 421001, China
关键词：
数据挖掘;燃料组件;堆芯;物理参数;快速预测
摘要：
反应堆堆芯核设计涉及大量方案的搜索与详细计算,缩短方案搜索时间有利于提高核设计效率.数据挖掘技术通过对大量数据进行学习与模式识别,可实现核设计方案物理参数的快速预测,更快地筛选出可行的备选堆芯方案.本文基于数据挖掘的决策树4种算法:C4.5、RepTree、Random Forest及Random Tree,在计算时以燃料富集度、含可燃毒物燃料棒数量及含量作为自变量,以寿期内keff不均匀系数偏差(KUCD)、径向功率不均匀系数偏差(RPNCD)、径向中子通量不均匀系数偏差(RFNCD)、堆芯寿期(CL)作为目标函数,构成目标函数符合度(CPF),利用大量已知核设计参数的组件及堆芯设计方案作为数据挖掘训练集,构建数据挖掘模型,并用于对未知核设计参数的组件方案集合(测试集)进行CPF快速预测.结果表明,4种算法利用训练集构建数据挖掘模型的时间在0.6 s以内,各算法的交叉验证精度均在0.7以上,其中C 4.5算法对C P F预测精度最高;对测试集方案的核设计参数预测中,单个方案的预测时间均在0.9 s以内,而Random Forest算法对CPF等于4的预测效果最好.
期刊：
Nuclear Engineering and Design,2020年360:110513 ISSN：0029-5493
通讯作者：
Yu, Tao
作者机构：
[Zhu, Weicong; Hui, Tianyu; Zeng, Wenjie; Xie, Jinsen; Chen, Lezhi; Yu, Tao] Univ South China, Dept Nucl Sci & Technol, Hengyang City 421001, Peoples R China.
通讯机构：
[Yu, Tao] U;Univ South China, Dept Nucl Sci & Technol, Hengyang City 421001, Peoples R China.
关键词：
Electric control equipment;Fused salts;Model predictive control;Molten salt reactor;Particle swarm optimization (PSO);Power control;Proportional control systems;Three term control systems;Control strategies;IMC-PID;Internal model control;Molten salt breeder reactors;MSBR;Nuclear reactor control;Particle swarm optimization algorithm;Reactivity disturbance;Controllers
