共查询到15条相似文献,搜索用时 125 毫秒
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一个新的中子倍增公式 总被引:5,自引:1,他引:4
本文用去耦合法解点堆中子动力学方程,导出了一个新的中子倍增公式。该公式计及了缓发中子效应,因此,与老的中子倍增公式相比,更好地描述了中子倍增的物理过程。 相似文献
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简要介绍了多重尺度摄动方法的原理,并运用多重尺度摄动法来解点堆中子动力学方程,导出新的次临界堆中子倍增公式,通过比较分析,证明新倍增公式包括了以前的公式,因而更精确、更实际地描述了中子倍增的物理过程。 相似文献
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为确定近临界系统内中子倍增因子随时间的变化与系统的反应性的关系,为反应堆启动提供参考,实验测量了中心中子在1个快中子临界装置3个次临界状态的中子倍增的时间行为,在反应性ρ=-2.27×10-3和-4.79×10-4的两个次临界状态下,阶跃加入反应性,分别等待180和450s后,中子密度(正比于中子倍增因子)才达到稳定值。与单群缓发中子假设计算的变化曲线比较表明,实验测量的中子倍增因子的变化比理论预估的变化快。即使如此,在反应堆启动中,仍需考虑中子倍增的延迟,以便推算正确的反应性。 相似文献
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反应堆物理实验中的源倍增法研究 总被引:6,自引:1,他引:5
给出了反应堆物理实验中临界测量和次临界度测量通常所采用的源倍增方法研究。首先从有源的扩散理论出发,导出了与以前不同的源倍增方法的公式。源倍增方法测量的参数实际是次临界系统在外源作用下的有源次临界中子倍增因子ks,而不是在这之前的中子有效倍增因子keff,然后研究了实验装置的临界质量,研究了ks与外源位置和能谱的关系,证明了导出的源倍增方法的理论是正确的。该方法可像过去那样用于反应堆物理实验中的临界外推测量,但不能用于次临界度测量。解决了长期困扰人们有关源倍增方法测量的参数问题。最后讨论了ks和keff的差别和关系以及对临界外推测量和核临界安全的影响。 相似文献
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利用MCNP程序建立了CFBR-Ⅱ堆结构的三维模型,借助中子倍增的方法实现了计算中子价值的功能。为消除实验中用中间钢托盘孔道内的中子价值代替上下半球的中子价值而引起的差异,利用均匀抽样技巧对各区域沿径向分层细致计算。结果表明,中子价值最大处位于高富集度铀区域中间某层而非系统中心或上下半球球心,其他区域中子价值则沿径向单调递减。 相似文献
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利用MCNP程序建立了CFBR-Ⅱ堆结构的三维模型,借助中子倍增的方法实现了计算中子价值的功能.为消除实验中用中间钢托盘孔道内的中子价值代替上下半球的中子价值而引起的差异,利用均匀抽样技巧对各区域沿径向分层细致计算.结果表明,中子价值最大处位于高富集度铀区域中间某层而非系统中心或上下半球球心,其他区域中子价值则沿径向单调递减. 相似文献
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核临界安全中的监督现场测量技术--源倍增方法的某些问题 总被引:1,自引:0,他引:1
给出了核临界安全中监督现场的测量技术——源倍增法的实验理论和实验方法。源倍增法实际测量的是有源次临界中子有效增殖系数k2而不是中子有效增殖系数Keff。在铀溶液核临界装置上进行了实验研究用源倍增法测量了次临界系统在外中子源作用下铀溶液不同液位的有源次临界中子有效增殖系数k2;用周期法测量了单位铀溶液位的反应性系数,然后用临界液位与次临界液位之差乘以单位铀溶液位的反应性系数,给出系统次临界液位时的反应性.由反应性给出传统观念上的中子有效增殖系数keff 。讨论了它们的差别及对核临界安全的影响。 相似文献
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《Journal of Nuclear Science and Technology》2013,50(10):422-424
The effect of neutron streaming upon the neutron multiplication factor in a fast critical assembly FCA-VI is estimated by considering the anisotropy of the diffusion coefficient. In this paper, the Benoist formula is adopted to obtain the diffusion coefficient. In his original expression, many effects such as those of neutron angular distribution, multiple collision (correlation of different neutron passes) and finiteness of lattice system are included. In order to estimate these effects, the generalized first-flight collision probability method is adopted as in the previous paper, and an improvement is brought over the previous method so as to calculate the effective diffusion coefficient in a practical slab lattice cell which is asymmetric about the center of the cell. Using the method of calculation described above, the anisotropic effect of neutron streaming in the lattices TA, TB, TC and TD used in the FCA VI-1 assembly is estimated. The effect of anisotropy of the diffusion coefficient upon the multiplication factor for the TA, TB, TC and TD lattices is found to be ?0.156, ?0.181, ?0.242 and ?0.330% δk/k, respectively. Usually, the effects of neutron distribution, multiple collision and anisotropic scattering are neglected in evaluating the diffusion coefficient when using the Benoist formula. Among these factors, the effect of multiple collision of neutrons has the largest effect upon the diffusion coefficient and upon the neutron multiplication factor. For the TA lattice, 30% of the overall effect of anisotropy is attributable to multiple collision. 相似文献
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Masao Komeda Akira Ohzu Takamasa Mori Yoshiaki Nakatsuka Makoto Maeda Masatoshi Kureta 《Journal of Nuclear Science and Technology》2017,54(11):1233-1239
The neutron multiplication effect appears when an item contains large amounts of nuclear material. The neutron multiplication effect in this paper means the effect of subsequent fission reactions which are caused by fission neutrons produced by interrogation neutrons from a neutron generator. The previous active neutron method could not distinguish between first-fission and subsequent-fission neutrons and might overestimate the amount of nuclear material. However, the neutron multiplication effect in the active neutron method has not been adequately investigated. We discuss the evaluation method of the multiplication effect in the fast neutron direct interrogation method, one of the active neutron methods, using simulations with the Monte Carlo code MVP and experiments involving uranium waste drums. The first-generation neutrons from an external neutron source generate fission neutrons called second-generation neutrons, the second-generation neutrons generate third-generation neutrons, and so on. This study supposes that the neutron multiplication effect is mainly caused by the third-generation neutrons under the condition that the fourth-generation neutrons are much fewer. This paper proposes a correction method for the neutron multiplication effect in the measured data. 相似文献
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