能谱变化对239Pu裂变室测量快中子注量的影响

热中子和共振区的中子在快中子临界装置中所占的份额很小,但是由于其相对大的截面,在慢化物存在的情况下,热中子和共振中子份额的微小变化,对^239Pu裂变室测量中子注量的结果影响很大。通过测量^239Pu裂变电离室在包镉和包硼、周围有无慢化物等情况下的反应率,Au、In活化片的镉比,S活化片在能谱变化下与^239。Pu的反应率比等,分析了快中子临界装置中热中子和共振区中子的分布,讨论了中子能谱变化对^239Pu裂变室测量快中子注量的影响及解决办法。     

基于活化法及MCNP程序的临界装置功率刻度

介绍了临界装置功率刻度的方法,在不同功率台阶下利用活化法测量临界装置的中子注量率分布及归一点的绝对中子注量率,并利用经修改编译的MCNP程序对临界装置的中子注量率分布进行校核计算。基于中子注量率测量及计算结果通过裂变率法计算不同功率台阶下临界装置的功率,同时外推到堆芯最大热中子注量率为1×10⁸cm^-2•s^-1时的功率,实现了临界装置的功率刻度。     

深次临界反应性测量中的动力学畸变效应修正

深次临界反应性测量中,随着次临界度的增加,中子注量率空间能谱分布偏离静态,由此产生的动力学畸变效应对次临界反应性测量产生影响。本文根据扩散理论分析次临界系统中子注量率空间能谱分布偏离的规律,并根据相对中子注量率计算动力学畸变效应修正因子。在零功率装置上进行4个不同棒态组合的次临界度测量试验。试验测量分析表明,随着次临界度的增加,动力学畸变效应修正因子从0.052逐渐增大到0.065,对应的反应性修正量为0.78eff³.01eff,可见,深次临界反应性测量中对动力学畸变效应进行修正是必要的。     

符合测量中子方法核查核弹头技术分析

用中子输运和与时间相关中子符合概率计算相结合的方法数值模拟低能外源中子照射下核弹头产生的裂变，以符合中子计数探测裂变事件发生率，以此核查核弹头的裂变特征。计算结果表明：在能量低于1MeV外源中子作用下进行符合中子测量，相应典型模型的核弹头的符合计数比用天然铀代替浓缩铀的相同结构的假核弹头的符合计数高1个量级，比其他散射中子的符合计数高几个量级。符合中子探测有可能用来认证核弹头的特性。     

加速器驱动次临界反应堆次临界度测量方法研究

以IAEA ADS基准题和日本京都大学KUCA实验装置为对象,对作者提出的次临界度测量方法[1]进行了更广泛的可行性验证。结果表明:对于局部区域功率变化引起的小扰动,通过改进表征中子注量率空间分布的特征参数,该方法仍然具有高的精度;而对于控制棒插入引起的大扰动,通过引入修正因子的方法,也仍然能准确测量次临界度。     

主动法探测贫化铀的实验研究

用有源（主动）的方法研究了贫化铀及其组合系统的中子诱发裂变缓发中子的探测技术。在不同质量和不同屏蔽体条件下测量和比较了贫化铀系统的裂变缓发中子随时间的分布,进一步分析了有源探测的入侵性和可核查性。探讨了采用缓发中子区分核与非核、贫化铀和浓缩铀系统的方法。     

小型平板铀裂变电离室研制

为了测量特定实验条件下狭小空间内中子注量率分布,研制了小型平板浓缩铀裂变电离室,该裂变室具有体积小、结构材料少等优点。论文叙述了裂变电离室的结构和制作工艺,通过测量自发衰变α粒子谱、裂变碎片谱对裂变电离室的性能进行了测试和评定,并标定了裂变电离室测量裂变碎片的探测效率。从指标上看,裂变电离室能达到设计要求和目的,可用于中子注量率的测量。     

柱形临界装置活性区组件中子增殖就地测量

为检验柱形临界装置活性区设计预留的徒手装配的安全裕度是否恰当,建立偏保守实验模型,开展中子增殖就地测量实验.通过逐步添加裂变系统部件模拟徒手装配状态,测量得到实验状态下的增殖值为2.67.该值低于GB15146.7-94规定的限值,证明活性区设计留有的安全裕度足够大,徒手装配时不存在临界安全问题.     

启明星1#次临界装置的裂变率分布

启明星1#次临界装置是我国为开展加速器驱动的次临界系统(ADS)研究而建立的国际上第1个具有快-热耦合结构的次临界反应堆实验装置。启明星1#次临界装置在确定的装载下、由不同能量的外中子源作用时,利用MCNP程序分别对装置快中子能谱区、热中子能谱区燃料元件的径向及轴向裂变率分布进行模拟计算,所使用外中子源的中子能量分别为2.5、5、14MeV。计算结果表明:在外中子源源强相同的情况下,源中子能量越高,裂变率越大;在源中子能量相同的情况下,次临界反应堆的轴向裂变率分布为中间高、两端低,径向裂变率分布在快中子能谱区先减小后增大,而热中子能谱区则是先增大后减小,然后,随着接近反射层又逐渐增大。该裂变率分布计算结果为后续实验测量和探测器布置提供了参考。     

浓缩铀柱形临界装置徒手装配临界安全检验

为完成徒手装配浓缩铀柱形临界装置临界安全检验实验,设计了基于薄膜装配的验证系统,以替代浓缩铀柱形临界装置上半部分结构。用MCNP程序计算了浓缩铀柱形临界装置上半部分及验证系统密合时的有效增殖因子keff。实验测得验证系统中心增殖不会超过12.50,满足徒手装配装置中心增殖限定值15的要求。实验结果表明,验证系统设计合理,徒手装配浓缩铀柱形临界装置是安全的。     

基于MCNP的缓发裂变中子衰减时间谱模拟计算

基于核裂变反应发生与缓发裂变中子发射这两个物理过程在时间上可相互分离的思想,利用MCNP程序计算得到了含铀地层0~100s范围内的缓发裂变中子衰减时间谱。模拟计算了球体几何模型中235 U与238 U核裂变反应率空间分布;借助SOURCE子程序依次对缓发裂变中子的发射位置、发射方向、发生核裂变反应的核素、缓发裂变中子所在的群组、发射时间及其初始能量等参数进行了抽样。结果表明,计算得到的缓发裂变中子衰减时间谱的时间特征与铀核素的缓发裂变中子群参数相符合。对缓发裂变中子总计数与地层铀含量之间的关系进行了线性拟合,拟合结果的相关系数平方值大于0.998 5,该结果从理论上验证了缓发裂变中子测井铀含量线性模型的正确性。     

Measurement and analysis of fission rates in depleted uranium and depleted uranium–polyethylene shells with neutrons from D-T reaction

To validate the concept design of a novel fusion–fission hybrid energy reactor, a depleted uranium assembly and a combined assembly of uranium and polyethylene were designed and assembled based on a depleted uranium spherical shell and a polyethylene spherical shell. The distribution of the fission rates for the depleted uranium and enriched uranium in the two assemblies, as a function of the distance of the detection position to the centre, was measured using a plate fission chamber bombarded by D-T neutrons. The addition of a polyethylene shell significantly changed the neutron spectrum; in particular, the neutron fluxes with energies of 1 MeV and lower were changed. Using MCNP5 and the attached libraries, the fission rate experiments were simulated, and the experimental configuration, including the wall of the experimental hall, was described in detail in the model. The fission rate distributions for depleted uranium and enriched uranium in the two assemblies were reproducible. The difference between the calculated results with different libraries and different tallies is as small as 1.0%. By considering the neutron flux, the fission rate and the C/E values, it is concluded that the fission rates of depleted uranium and enriched uranium induced by the fast neutrons were overestimated, and it is proposed that the fission parameters of uranium for fast neutrons should be re-evaluated, or the margin of the concept design should be enlarged, to make the concept effective.     

24.4KeV中子诱发^235U裂变的产额测量

一、前言 对~(235)U热中子裂变已经作了充分的研究,裂变产物的产额作了广泛的测量,并对实验数据进行了多次编评。但是对于其它单能中子诱发~(235)U裂变研究还远远不够,尤其是keV能区的中子更是如此。J.G.Cuninghame等测量了130-1700keV中子诱发~(235)U裂变中一些核素的产额。但是低于130keV中子诱发的裂变研究,文献中未见过报道。为了研究产额随中子能     

有源符合中子法探测高浓缩铀的技术研究

开展了有源符合中子法探测^235U富集度为90．34％的小圆柱状金属铀块裂变材料的方法与技术研究。使用有源井型中子符合计数装置测量金属铀块中^235U受Am-Li中子源诱发后产生的裂变中子,运用最小二乘法的计算方法将测得的中子总计数率、真符合计数率分别与金属铀块质量做线性拟合,其线性相关性系数达0．999;在此基础上,进一步测量了在相同质量金属铀的条件下不同源、样距及不同样品形状的中子计数变化趋势。     

符合中子法测量贫化铀部件质量技术研究

分别采用有源（主动）及无源（被动）符合中子法研究了贫化铀半球壳部件质量的测量方法与技术。采用井型中子符合计数器对不同质量的贫化铀部件进行了符合中子计数的测量,主动法测量选取Am-Be源作为诱发中子源,通过屏蔽体减小源中子偶然符合计数的影响,根据测量结果求出的贫化铀部件线性拟合质量与标称质量最大相对偏差达11.71%,而被动法测量的拟合质量最大相对偏差仅为4.05%。证明了由于与主动法相比减弱了形状的影响,采用被动法测量贫化铀部件质量精度更高且更为可靠。     

3 MeV中子诱发裂变测定铀同位素丰度

铀同位素丰度分析是核燃料循环中重要的分析项目。本工作研究了以D(d,n)³He反应产生的能量约为3 MeV的中子为源诱发裂变测定铀同位素丰度,并与以T(d,n)⁴He反应产生的14 MeV快中子为源的方法进行了比较,结果表明两种方法分析结果基本一致。     

Study of the neutron multiplication effect in an active neutron method

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.     

在特定实验条件下的散射中子本底研究

研究了d-T中子源与探测器距离较近时,扣除实验大厅散射中子本底的方法。实验上采用屏蔽法,用了铀裂变电离室。用MCNP/4A程序和FENDL2库数据计算了实验大厅散射中子本底曲线。采用实验和计算相结合的方法扣除了在特定实验条件下的散射中子本底,方法是可行的。     

Experimental study of neutron counting in a zero-power reactor driven by a neutron source inherent in highly enriched uranium fuels

Even a zero-power reactor core containing highly enriched uranium has a weak neutron source inherent in uranium 235, and consequently, a neutron counter placed closely to the core without external neutron source registers a certain counting rate. The study of the counting is very important for zero-power reactor physics experiments with a high precision. In this experimental study, first, at a shutdown state of the UTR-Kinki reactor without start-up neutron source, a pulse height distribution of output signals from a neutron proportional counter was measured to confirm that these signals resulted from neutron detections. At several subcritical states of the UTR, then, the Feynman-α analysis was carried out to confirm that the neutrons detected by the counter must be fission neutrons multiplied by fission chain reactions. The correlation amplitude measured in the Feynman-α analysis was much higher than that measured in a previous drive by start-up source. Further, it was also confirmed that the subcriticality dependence of neutron counting rate followed the source multiplication formula. This feature indicated that the one-point model was very successful in the subcritical range including the shutdown state.