HTR-PM中~(14)C产生与释放行为研究

~(14)C具有较长的半衰期,可与稳定同位素一起进入生物圈,从而在核电站的环境影响评价中受到关注.本文基于HTR-PM给出了产生~(14)C的各反应模型,并代以HTR-PM参数,对HTR-PM中~(14)C的年产生量和气态释放量作出估算.最后,将计算结果与CANDU堆型进行了比较.     

GASFLOW应用于HTR-PM冷却剂排放事故分析

模块式高温气冷堆(HTR-PM)在冷却剂排放事故下的舱室承压能力是反应堆安全分析的重要对象。通过对FLUENT、GASFLOW和RELAP5的计算结果进行对比分析,发现GASFLOW因其兼顾计算效率与计算结果合理性的特性,最适合反应堆舱室在冷却剂排放事故下的承压计算。     

Effects of reaction temperature and inlet oxidizing gas flow rate on IG-110 graphite oxidation used in HTR-PM

The oxidation behavior of a selected nuclear graphite (IG-110) used in Pebble-bed Module High Temperature gas-cooled Reactor was investigated under the condition of air ingress accident. The oblate rectangular specimen was oxidized by oxidant gas with oxygen mole fraction of 20% and flow rates of 125–500 ml/min at temperature of 400–1200?°C. Experiment results indicate that the oxidation behavior can also be classified into three regimes according to temperature. The regime I at 400–550?°C has lower apparent activation energies of 75.57–138.59 kJ/mol when the gas flow rate is 125–500 ml/min. In the regime II at 600–900?°C, the oxidation rate restricted by the oxygen supply to graphite is almost stable with the increase of temperature. In the regime III above 900?°C, the oxidation rate increases obviously with the increase of temperature. With the increase of inlet gas flow from 125 to 500 ml/min, the apparent activation energy in regime I is increased and the stableness of oxidation rate in regime II is reduced.     

模块化高温气冷堆反应堆设计重点安全问题分析

本文介绍了模块化高温气冷堆的安全特点,对反应堆堆芯设计核安全审评重点关注的核安全问题进行了分析,并提出解决方案以供设计和审评人员参考。     

石墨堆芯结构在地震激励下动态响应的数值模拟

模块化高温气冷堆（HTR-PM）石墨堆芯结构是多体结构,其动态特性研究是复杂的非线性问题。国内外开展了一系列研究,未能较好解决。为了分析该非线性结构的动态特性,本文介绍一种数值模型,将石墨砖和碳砖简化为质点,各部件的接触简化为连接器单元,通过碰撞试验拟合获取连接器参数。数值模型计算的位移基本同1∶1双层四砖石墨组件试验位移时程结果吻合。分析证明,模型对参数不敏感,计算结果准确高效。因此,可将此模型用于石墨堆芯结构的位移分析。     

HTR-PM大范围变负荷的MA自适应优化算法

为应对电网负荷需求的变化，球床模块式高温气冷堆核电站示范工程(HTR-PM)在设计上具备大范围变负荷运行以满足电网负荷的能力。由于无法获得大范围变负荷精确适用的模型，使得基于模型的操作优化面临挑战。为处理模型与对象的失配，提出HTR-PM大范围变负荷的MA(modifier adaptation)自适应优化算法。MA自适应优化算法利用过程反馈信息修正优化模型，促进优化模型与对象优化命题的一致性，进而有助于基于模型的操作优化收敛至对象的最优操作。借助信赖域框架，MA自适应优化算法可基于模型评价自适应更新模型、调整修正的优化模型的应用范围，确保在合适操作空间内求解优化模型。而且，信赖域框架还降低了算法性能对算法参数的敏感性。MA自适应优化算法在HTR-PM双堆同步大范围变负荷中的应用验证了方法的有效性。     

High temperature reactor development in China

Since the late 1970'-s the research and development program on the high temperature gas-cooled reactor (HTR) has been carried out in China. The 10 MW High Temperature Gas-cooled Reactor-Test Module (HTR-10) reached first criticality in 2000 and was put into full power operation in 2003. Six safety demonstration tests were done on the HTR-10. The project of the HTR-10 with a gas turbine cycle is underway. The project of the HTR demonstration plant with a power of around 150 MWe (HTR-PM) is planned. In this paper the HTR development in China is briefly described.     

HTR-PM蒸汽发生器绝热层支撑结构的设计与分析

为提高HTR-PM高温气冷堆蒸汽发生器的热交换效率并分隔冷热氦气的通路,必须在蒸汽发生器中设置绝热装置.在围绕换热管放置的钢制围筒上铺设一定厚度的绝热纤维,用多块覆盖板将绝热纤维压紧,在每块覆盖板中心与四角,用中间填充绝热纤维的螺栓将覆盖板定位并紧固,组成绝热层支撑结构.使用有限元方法对绝热层支撑结构在绝热材料压力、蒸汽发生器失压、地震等多种载荷的综合作用下的应力分布情况进行计算,计算结果表明:支撑结构在多种载荷的作用下仍能保持绝热层功能的可靠性与结构的完整性.     

Radiological habitability evaluation of the control room of the high-temperature reactor pebble-bed module: post-accident dose assessment and sensitivity studies

The radiological habitability of a control room is important for nuclear emergency response, which is also a licensing prerequisite for nuclear power plants. It is determined by both atmospheric relative concentrations and doses received via different pathways. However, most recent studies have focused only on the former, which may not be adequate. The present study therefore investigates the radiological habitability and its sensitivity to different parameters in the high-temperature gas-cooled reactor pebble-bed module power plant. For three typical accidents, the study estimates the body, thyroid and skin doses received via different pathways using the Nuclear Regulatory Commission recommended ARCON96 and dose calculation method in RG 1.195. To make a realistic evaluation, the latest design and site-specific information, including the unique accidental source term, are collected and used as input parameters. The evaluation results reveal that the total dose of different pathways in the control room is far below the limit, which demonstrates the effectiveness of the current design. The inhalation exposure is the dominant pathway, and iodine and caesium are the primary contributors of the inhalation dose. The particle filter removal fraction is the most influential parameter in an accident which the activities of metal radionuclides are high.     

基于THERMIX/BLAST和vPower平台的HTR-PM启停堆过程仿真分析

将THERMIX/BLAST程序嵌入至vPower仿真平台,开发球床模块式高温气冷堆示范电厂(HTR-PM)工程模拟机。在该工程模拟机上进行双堆冷启动过程和双堆正常冷停堆过程的模拟仿真,分析2种工况中反应堆功率、氦气流量、蒸汽发生器出入口参数及汽轮机入口蒸汽参数等关键参数的变化趋势,总结双堆冷启动过程和双堆正常冷停堆过程的运行特点。结果表明,2个反应堆在运行过程中互相影响,二回路参数变化是2个反应堆耦合的结果。