共查询到20条相似文献,搜索用时 187 毫秒
1.
离子法向轰击单元素靶溅射产额的解析估算 总被引:1,自引:0,他引:1
给出了计算离子法向轰击单元素靶溅射产额的通用解析公式,将该解析公式估算值、蒙特卡罗模拟值与相应实验数据进行了比较,并用Wilcoxon配对符秩检验法研究了上述结果的显著性差异。 相似文献
2.
在核数据评价和测量中,经常遇到同一物理量观测值的处理。当这些数据在统计学上一致时,很容易用统计方法处理,但存在系统误差时,处理就很困难。本文提出了一个普遍适用的方法。根据这个方法,由给出的系统误差的协方差矩阵,可计算平均值和它的误差。加权平均值、算术平均值、内误差、外误差和算术平均误差只是这个方法的特殊情况。给出的实例表明,这个方法是合理的。 相似文献
3.
介绍了脉冲反应堆脉冲功率波形信号的时域表达式,用积分变换方法对脉冲功率信号的特征做了初步的理论分析,求出了频率密度函数的由功率测量仪表响应特性引入误差的计算公式,并给出了脉冲功率波形信号的复频域模型。分析结果表明,信号频谱存在着一个临界频率,只要测量仪表通频带上限高于此频率,仪表响应特性所引入的误差就可基本消除。 相似文献
4.
如何从寿命谱曲线中分析并给出各种成份的寿命、强度和相应的误差估计,是大家关心的问题。本文以多指数函数为拟合函数,利用最小二乘法原理给出拟合的计算公式,导出误差分析公式。并用ALGOL语言编制了通用程序。最后,给出二、三指数计算结果。 相似文献
5.
熊正隆 《核标准计量与质量》2002,(4):7-22
本文简要介绍了有关误差的术语,对测量用核仪器(包括提供被测量的核仪器)的误差测定作了简化和约定,规定了其相对固有误差,重复性误差,非线性,不稳定性以及温度,湿度和交流供电电压的影响误差统一的表示,测量和计算方法,并给出最大工作误差由单项误差合成的计算公式和直接的测量方法。 相似文献
6.
7.
8.
对各种双脉冲信号通过单道脉冲幅度分析器时可能产生的各种误差进行分析。给出各种双脉冲信号在单道中传输时各点的波形图。对各种双脉冲信号产生的误差对单道计数产生的影响进行分析。基于误差分析对单道使用时注意事项给出建议。 相似文献
9.
熊正隆 《核标准计量与质量》1998,(4)
针对核仪器标准“未进行误差合成而不能给出最大工作误差”和“单项误差的测量、计算方法不同”两个问题带来的困难,建议制定“核仪器测量的误差”标准。通过研究误差理论和分析现行核仪器标准中关于误差合成计算公式,本文提出了误差合成的计算方法以及统一固有误差、重复性、不稳定性和非线性等误差的测量和计算方法的具体建议。 相似文献
10.
11.
为了测试反应堆控制和保护系统的嵌入式软件,将手工静态测试方法和动态仿真测试方法组合使用(简称组合测试).组合测试分为2步,即先用手工静态测试方法验证可编程逻辑控制器( PLC)嵌入式软件的安全性与合理性,再用动态仿真测试方法验证其功能的有效性.组合测试只要有通用个人计算机(PC)和待测软件的开发及仿真工具即可实施.在实际的PLC运行环境中运用硬件测试方法,对组合测试的有效性进行验证.结果表明,组合测试是有效的,且比硬件测试方法的测试效率更高. 相似文献
12.
13.
Fault current tests of ITER external bypass are performed to verify its fault suppression capability. This paper describes the test requirements, test schemes and test procedures of fault current test for external bypass. The effectiveness of test schemes for fault current tests is verified by the simulation results and test results based on DC test platform. 相似文献
14.
Transient fault current test of ITER DC reactor is performed to verify the fault suppression capability of DC reactor. In this paper, the research background, test scheme and test platform of transient fault current test of ITER DC reactor are presented in the first place. The next, the test requirements and acceptance criteria are presented. Finally, the calculation and simulation for DC test platform of ASIPP are presented, and the effectiveness of test scheme is proved by the simulation result and the test results based on DC test platform. The contents presented in this paper can be available for short-circuit test of DC reactor with large current. 相似文献
15.
16.
法系核电厂核岛压力容器根据在役检查规范和大纲的要求需要实施定期水压试验,但部分容器由于系统设计的原因不能用液体实施水压试验,只能执行气压试验。本文对比分析了国内外规范对于气压试验的实施要求,并结合核岛安装阶段的气压试验过程,选定了核岛压力容器气压试验的试验压力、试验介质、验收标准等;同时结合容器水压试验的风险分析和辐射防护要求,制定气压试验的防护措施。根据以上试验参数与风险防护措施,在某核电厂核岛成功实施了压力容器气压试验,为后续的在役阶段核岛压力容器气压试验提供重要参考。 相似文献
17.
为保证岭澳核电站环形吊车载荷试验(特别是双钩联合抬吊静载试验)的顺利进行.对环形吊车的试验工具和试验方法进行了技术改进。本文简要介绍了百万千瓦级压水堆核电站环形吊车静载荷试验的技术要求、常规试验方法和岭澳核电站环形吊车静载荷试验的改进措施。 相似文献
18.
Katsuyuki Shibata Toshihiro Oba Takaichi Kawamura Shohachiro Miyazono Norio Yokoyama 《Nuclear Engineering and Design》1981,66(1)
Fatigue and fracture tests of piping models with flaws in the inner surface were carried out to investigate the fatigue crack growth, coalescence of multiple cracks and fracture behavior.Two straight test pipes with and without weldment in the test section of AISI type 304L stainless steel were tested under almost the same test conditions by imposing moment loads. Three artificial defects were machined in the inner surface of the test section of the test pipes and the fatigue test was performed until the cracks coalesced and grew through the thickness. Subsequently, a static load was imposed on the test pipe which contained a large crack in the test section.The fatigue test results are compared with an analytical crack growth behavior predicted by the method described in the Section XI of ASME Code, and show slower crack growth than that of the prediction. From the fracture test results, it is found that the test pipes can endure considerably high load. 相似文献
19.
放射性物质运输货包安全试验 总被引:3,自引:1,他引:2
介绍了中国放射性物质运输遵守的法规和中国辐射防护研究院用于放射性物质运输货包试验的下落试验设施、耐热试验设施和数据获取能力。试验设施根据IAEA的《放射性物质安全运输条例》(TS-R-1)和中国的《放射性物质安全运输规程》(GB 11806-2004)的要求建设。下落试验设施能用于13 t级以下的A型和B型货包的自由下落试验、贯穿试验、力学试验(自由下落试验Ⅰ、自由下落试验Ⅱ和自由下落试验Ⅲ)。耐热试验设施能完成B型货包的耐热试验。利用这些设施已进行了FCo70-YQ型货包、30A-HB-01型货包、SY-I型货包和XAYT-I型货包的遵章取证试验 相似文献
20.
The effects of nonmetallic impurities on the compatibility of liquid lithium with molybdenum, TZM, niobium, type 304 and type 316 stainless steels, nickel and Hastelloy N were investigated. Three compatibility tests (test I, test II and test III), classified by the grade of air contamination of the lithium, were conducted at 600°C for about 1000 h in stainless-steel vessels. In each test the above-mentioned specimens were immersed together in the lithium. In test I weight gain was observed for all the specimens except nickel and Hastelloy N. However, in test II and test III, weight loss was observed for all the specimens. MoNi3 was produced on the surface of the molybdenum and TZM specimens as a result of the reaction between molybdenum and nickel dissolved in the liquid lithium. NbN0.9O0.1 was observed on the surface of niobium specimens in test I and test II, and Nb2N in test II and test III. The surface of the stainless-steel specimens in test II and test III was depleted with nickel and chromium elements, and deteriorated. The corrosion rates of the test specimens in test III were about 2, 5, 26 and 22 μm/yr for molybdenum or TZM, niobium, type 304 stainless steel and type 316, respectively. Nickel and Hastelloy N were severely attacked by liquid lithium at 600°C. These results were obtained for liquid lithium with a high nickel concentration. 相似文献