共查询到14条相似文献,搜索用时 343 毫秒
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为确定堆芯γ射线对自给能探测器输出信号的影响。将钒和铑自给能探测器放置在试验堆某一稳定的中子和γ辐照水平下,通过停堆给自给能探测器施加一个中子注量率阶跃信号,观察探测器输出信号的变化来推断γ射线对自给能探测器输出信号的影响。 相似文献
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杨有琏 《核电子学与探测技术》1989,9(3):135-141
本文给出了铑自给能探测器的热中子灵敏度和中子灵敏度的理论计算公式、燃耗修正公式以及不同中子温度下的换算公式。运用这些公式对ZTRh 123型铑自给能探测器的热中子灵敏度和中子灵敏度进行了理论计算,并在反应堆中对其进行了实验验证。其结果表明,理论计算值和实验标定值是相吻合的。其偏差:热中子灵敏度为8.5%,中子灵敏度为3.9%。 相似文献
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本文介绍了铑自给能中子探测器的应用原理及结构,灵敏度理论分析及刻度,对变化通量的响应,线性工作范围,长期辐照性能,伏安曲线等内容。 相似文献
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研究推导出了发射体采用圆柱体拉丝工艺的β衰变自给能中子探测器灵敏度计算公式和β电子在绝缘层内的逃逸因子(K_g)计算公式。计算绘制了绝缘层与K_g的关系曲线。研究发现文献[1]提供的K因子图存在偏差,不适合直接应用于探测器研发。计算给出了相同机械尺寸的钒和铑探测器在恒定中子场内灵敏度随累积中子照射时间变化趋势曲线,参考堆芯中子通量分布仿真结果提出灵敏度修正需考虑堆芯轴向中子通量分布影响的观点。 相似文献
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铑自给能探测器延迟响应消除算法研究 总被引:1,自引:0,他引:1
简单介绍了核电站堆芯核测系统的铑自给能探测器工作原理和结构,详细描述了铑自给能探测器响应延迟消除算法以及其在核电站的应用. 相似文献
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铑自给能探测器(RSPND)输出电流信号的慢响应特性严重影响反应堆内中子注量率的实时测量,不利于反应堆的控制和安全管理。采用反函数计算或各种补偿方法改进其响应特性,有利于RSPND的使用。本文研究了前向差分变换法、后向差分变换法、阶跃响应不变法及双线性变换法等4种数字处理算法,有效缩短了铑自给能探测器输出信号的响应时间,时间常数缩短到5 s以内。通过数字实验系统,验证了算法的正确性,为该探测器用于反应堆内中子注量率测量的快速响应提供了可行性。 相似文献
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简单介绍了核电站堆芯核测系统铑自给能探测器结构、工作原理、电流产生过程,并对自给能探测器电流计算方法和影响电流测量的相关因素进行了详细介绍和研究. 相似文献
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This paper describes the experimental demonstration of the theoretical result of the previous work on LMI (linear matrix inequality) based H∞ filter for time-delay compensation of self-powered neutron detectors. The filter gains are optimized in the sense of noise attenuation level of H∞ setting. By introducing bounded real lemma, the conventional algebraic Riccati inequalities are converted into linear matrix inequalities (LMIs). Finally, the filter design problem is solved via the convex optimization framework using LMIs. The experimental measurements of rhodium detector signal from a research reactor show that the predicted theoretical filter performance is verified by showing successful reconstruction of the reference power signal. 相似文献
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The in vessel instrumentation of sodium-cooled fast reactors must deliver measurements that are reliable and easy to interpret over several reactor cycles in order to fulfill the safety requirements. This paper compares, with respect to this requirement, three types of detectors that are widely used in neutron measurements: fission chambers, boron-lined proportional counters, self-powered neutron detectors. We use neutron spectra that are computed for preliminary design of sodium-cooled fast reactor in different representative locations: in diluting tubes within nuclear fuel assemblies, or in the lateral neutron protections. With an evolution code, we compute the expected signal for each type of detector, to assess whether its level is sufficient, and also its evolution over three operating cycles, to examine whether it is compatible with long term measurements. The conclusion is that fission chambers are the only type able to deliver an interpretable signal for a wide dynamic of reactor power and for three or more operating cycles. The two other types are shown to be inadequate. 相似文献
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从故障现象、原因排查和解决措施三个方面,分析了我国核电厂近期发生的堆外中子测量系统闪发高计数率异常中所涉及的电缆接头问题和探头故障问题,提出了核电厂应关注堆外中子测量系统设备制造和安装的质量等建议,为解决和避免类似的堆外中子测量系统闪发高计数率问题提供借鉴。 相似文献