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机构地区:[1]清华大学核能与新能源技术研究院,100084,北京
出 处:《高技术通讯》2005年第10期68-72,共5页Chinese High Technology Letters
基 金:国家科技攻关项目
摘 要:根据高温气冷实验堆HTR-10的运行特点和控制要求,利用清华大学核能与新能源技术研究院开发的用于仿真计算的系统--10MW HTR-10仿真控制支持系统,进行了HTR-10满功率下动态特性的仿真研究,研究了HTR-10满功率时在外加反应性、氦流量、给水流量变化下的动态特性规律,并将得出的系统动态响应的仿真结果与反应堆在3MW低功率运行时的试验结果作了比较,发现动态特性变化规律一致,验证了仿真控制支持系统的准确性,同时获得了HTR-10满功率下的主要动态特性:由于HTR-10具有很大的负温度反馈系数,只用控制棒很难调节堆功率;而氦流量的变化对堆功率影响很敏感,二者几乎成线性变化,适于负荷变化的功率调节;给水流量的变化对核功率和热氦温度等一回路的参数影响不大,但对蒸汽温度等二回路参数影响显著,适合于蒸汽温度的调节.The integrated system for simulation, control design and online assistance of the HTR-10 (HTRSIMU) has been developed for simulation by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University. Using this simulation system, the dynamic characteristics of HTR-10 at full power operation were studied when external reactivity, helium flow and feed-water flow were changed separately. Compared with the test results obtained at the reactor' s partial load operation of 3MW, the simulated characteristics are consistent with experimental results. So the HTRSIMU is thus validated and then the main dynamic characteristics of HTR-10 at full power are studied: Control rod can not regulate the reactor power well separately because of the strong negative temperature feedback coefficient of HTR-10; The reactor power is sensitive to the change of helium flow and almost changes with helium flow linearly, so the change of helium flow is appropriate for power regulation while load changing hot helium temperature in the primary loop and has used to regulate steam temperature. ; The change of feed-water has little influence on nuclear power and much influence on steam temperature in second loop, so it can be used to regulate steam temperature.
关 键 词:HTR-10 仿真 系统 动态特性 10MW高温气冷实验堆 满功率 特性研究 支持系统 流量变化 运行特点
分 类 号:TL424[核科学技术—核技术及应用] TN934.1[电子电信—信号与信息处理]
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