Fission cross-sections of U and Pu averaged over Cf neutron spectrum

A series of measurements have been carried out to derive values for the spectrum-averaged fission cross-section of ²³⁵U and ²³⁹Pu for ²⁵²Cf fission neutrons. Two nearly identical target foils were mounted on either side of a Cf source (10⁷ neutron/sec) in a compensated beam geometry. Fission fragments passing through limited solid angle apertures were recorded from each foil by solid-state track-etch techniques. The Cf neutron source strength was calibrated in manganese bath relative to the standard source NBS-II. Values of 1.215 ± 0.022 barn for ²³⁵U and 1.790 ± 0.041 barn for ²³⁹Pu were obtained for the fission cross-sections, corresponding to a ratio value of 1.473 ± 0.041.     

^252Cf微型快裂变室

本文叙述的快裂变室主要用于~(252)Cf裂变中子飞行时间谱测量。该裂变室具有重量轻(1.65g)、上升时间快(6ns)、对裂变碎片探测效率>99％等特点。针对裂变中子能谱测量的特殊要求,详细论述了裂变室设计应遵循的基本原则及其对能谱测量可能带来的影响。     

Prompt fission neutron spectrum evaluation for 252Cf(SF) in the frame of the multi-modal fission model

In the present work, an attempt to improve the evaluation of the prompt fission neutron spectrum of ²⁵²Cf(SF) is made. The multi-modal fission concept is included into the Los Alamos model. A more generalized form of the fission fragment residual nuclear temperature distribution and a possible anisotropy effect of the prompt neutron emission in the center-of-mass system are taken into account, too. The multi-modal fission parameters entering the prompt fission neutron spectrum model are determined on the basis of the experimental data concerning the fission fragment total kinetic energy TKE(A) and mass distribution Y(A) measured at IRMM. The calculated prompt neutron spectrum is obtained in better agreement with the standard point-wise evaluation of Mannhart and compared to other evaluations made with different models.     

^252Cf中子分布条件下的中子探测效率测量

利用BC-501A探测器测量了252Cf自发裂变中子源,得到不同中子阈能的252Cf中子分布条件下的中子探测效率,实验得到了252Cf中子源的核温度T=1.42±0.03MeV.     

252Cf源中子辐照装置的设计及性能测试

介绍了一种具有可变准直孔低γ本底的252Cf源中子辐照装置.对其中子辐射场和中子屏蔽性能的测试结果表明,该辐照装置能够形成稳定的中子场,屏蔽体对252Cf中子源有很好的屏蔽性能.     

Measurement of the total neutron cross sections for250,251Cf

V. I. Lenin Scientific Research Institute of Atomic Reactors. Translated from Atomnaya Énergiya, Vol. 74, No. 1, pp. 72–75, January, 1993.     

Response Measurement of Three Scintillation Detector to Instantaneous Rays from 252 Cf Fission

应用飞行时间谱,测量了LaCl3(Ce)、BC400、ST401三种闪烁探测器对252Cf裂变γ射线和中子的响应,获得了信号输出波形参数、定时精度、不同中子能量阈值的计数.测量了LaCl3,(Ce)探测器被高密度聚乙烯屏蔽后的响应.BC400探测器对入射γ射线的定时精度为1.3ns,ST401为1.5 ns.通过匹配快响应光电倍增管,LaCl3 (Ce)探测器是混合场中测量γ射线时间序列的一种有效方法.     

Response Measurement of BC501 Detector to Instantaneous Rays from 252Cf Fission

为了应用BC501液体闪烁探测器测量脉冲信号时间序列,利用252Cf裂变γ射线和中子飞行时间谱,测量了两种大小BC501探测器对裂变瞬发射线的响应.探测器对入射γ射线的定时精度能够达到1.2ns.获得了平均一次252Cf裂变,不同中子能量阈值以上,γ射线和中子的绝对计数.     

10^6量级^252Cf自发裂变中子源用屏蔽操作柜设计

描述了106量级252Cf自发裂变中子源用屏蔽操作柜的研制情况.介绍了该屏蔽操作柜的设计原则、设计考虑、屏蔽计算和屏蔽材料的选择.并用小强度源实际测量屏蔽操作柜性能.研制的屏蔽操作柜材料从外到内为不锈钢外壳(2mm)、聚乙烯(150mm)、不锈钢内壁(20mm).在操作者操作位置处中子屏蔽达到9倍,γ屏蔽达到近3倍.结果表明该屏蔽操作柜能满足操作人员实际操作需要和所受剂量限值要求.     

Simulation and experimental study of a random neutron analyzing system with （252）~Cf neutron source

Experiments were performed on a high-speed online random neutron analyzing system(HORNA system)with a 252Cf neutron source(up to 1 GHz sampling rate and 3 input data channel),to obtain time-and frequencydependent signatures which are sensitive to changes in the composition,fissile mass and configuration of the fissile assembly.The data were acquired by three high-speed synchronized acquisition cards at different detector angles,source-detector distances and block sizes.According to the relationship between 252Cf source and the ratio of power spectral density,Rpsd,all the signatures were calculated and analyzed using correlation and periodogram methods.Based on the results,the simulated autocorrelation functions were utilized for identifying different fissile mass with Elman neural network.The experimental results show that the Rpsd almost remains at constant amplitude in frequency range of 0-100 MHz,and is only related to the angle and source-detector distance.The trained Elman neural network is able to distinguish the characteristics of autocorrelation function and identify different fissile mass.The average identification rate reached 90% with high robustness.     

^252Cf快响应电离室裂变中子、γ飞行时间谱测量

介绍了252Cf快响应电离室裂变中子、γ飞行时间谱的测量系统的组成及工作原理,并给出了测量结果.这个系统测得的中子、γ飞行时间谱,其γ峰的半高宽达到0.9 ns,可应用于探测系统的定时精度测量、n-γ分辨效果的检验等.     

Representation of the fission neutron spectrum of235U,239Pu, and252Cf and the reactor spectrum as a superposition of five inelastic scattering functions

The results of investigations of the representation of the fission neutron spectra of²³⁵U,²³⁹Pu, and²⁵²Cf and neutron spectra at the core center of fast reactors as a superposition of five Weisskopf functions are presented. This representation best reflects the physics of nuclear fission and shows that the spectra at the core center of fast reactors are reconstructed with an error close to the error of the best studied spectra in the worldwide practice of neutron measurements. 3 tables, 13 references. All-Russia Scientific-Research Institute of Physical-Technical and Radio Engineering Measurements. Translated from Atomnaya énergiya, Vol. 88, No. 4, pp. 292–299, April, 2000.