1.4MeV-5MeV中子诱发~(238)U裂变产额测量

~(238)U裂变产额测量工作在核数据测量中有着重要意义,本工作利用2.5MeV质子静电加速器产生的1.4MeV-5MeV单能中子诱发238U裂变,通过对裂变产物放射性的测量对裂变产物核素~(135)I、~(133)I、~(105)Ru和~(91)Sr的产额进行了测定。照射过程中中子通量用活化法确定。分析了影响实验测量的多个因素,包括用MCNPX程序对中子在靶头及样品中的多次散射和自屏蔽效应进行了修正,对γ射线在样品中的自吸收进行修正等。得到产额数据典型误差为3.5%,最后把测量结果与已有的裂变产额数据进行比对。     

单能中子诱发~(235)U和~(238)U裂变的产物产额

本文利用碎片质量分布5-Gauss半经验公式,计算了单能中子诱发~(235)U和~(238)U裂变放中子前碎片产额,并采用七点拟合公式和线性内插方法求得碎片发射的中子产额。然后按照Terrell给出的转换方法,把放中子前碎片的产额换算为放中子后产物的产额。具体计算了_(40)~(95)Zr、_(58)~(144)Ce、_(60)~(147)Nb三种产物产额随入射中子能量的变化关系,并与实验观测结果作了比较。     

用产额比测量~(235)U/~(238)U同位素丰度比

用裂变产额比法测量了样品中235 U/238 U同位素丰度比。样品受14.8MeV中子短时间辐照后,用HPGe谱仪系统跟踪测量其γ能谱,从各自的特征峰分析得到不同裂变产物的加权平均产额,得到了若干对产物核素的产额比与丰度比的相关曲线。     

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     

DF-Ⅵ堆中心平均裂变截面比~(238)■_f/~(235)■_f计算

计算和测量反应堆芯部可裂变材料的平均裂变截面比,使有可能估算出堆芯部中子能谱的硬化程度。计算和测量~(238)U和~(235)U的平均裂变截面比~(238)■_f/~(235)■_f,就能估算出堆芯部~(238)U裂变阈1.4 MeV以上的中子份额。用固态核径迹探测器法已测得DF-VI堆芯部     

由~(137)Cs,~(144)Ce和~(148)Nd为监测体测定燃耗中的辐照史校正方法

在通过测定~(137)Cs,~(144)Ce,~(148)Nd等裂变产物监测体浓度推算辐照燃料燃耗的方法中,需要裂变产物的平均裂变产额、(n,γ)俘获反应的修正量、放射性裂变产物的堆内衰变修正量,可裂变核素的平均裂变能量等参数。这些参数是同燃料的辐照历史密切相关的。本文介绍一种计算这些参数的方法、计算机程序概况和计算结果。本方法有下述特点:1.采用燃耗物理计算获得的可裂变核素核密度及裂变截面作为本程序的输入数据。2.采用燃耗值的初始实验结果反推燃料辐照期间的中子通量。3.精确计算了~(137)Cs和~(148)Nd两种监测体(n—1)衰变链和n衰变链中子俘获反应的修正量。从而提高了各种参数的精确度。对于浅燃耗天然铀辐照燃料的应用例,计算结果表明,~(137)Cs,~(144)Ce,~(148)Wd获得燃耗结果的修正量分别为 0.29%, 16.40%,-2.75%。本方法对燃耗结果可能引入的误差分别为±0.1%,±0.3%,±0.6%。     

~(252)Cf自发裂变中子诱发~(235)U裂变~(99)Mo累计产额测量

一、引言 裂变谱中子诱发~(235)U裂变~(99)Mo累计产额一直存在较大分歧。首先,苏联在五十年代测量的两个结果就相差8％。以后的测量结果虽然差距减小,但仍分为两组,彼此相差5％;一组接近苏联的高值6.4,另一组接近并稍低於热中子诱发~(235)U裂变的~(99)Mo累计产额6.14。在裂变产物产额的测量中,~(99)Mo往往被取作参考核,其产额数据的上述分歧,影响其他裂变产物产额的取值。因此,我们对其进行了测量。     

14兆电子伏中子引起的~(238)U裂变截面的测量

我们以T(d,n)~4He反应为中子源,用半导体探测器测量伴随α粒子的方法确定中子通量。在中子能量为14.10±0.10,14.60±0.20和15.04±0.13兆电子伏处绝对测量了~(238)U的裂变截面。     

0.57 MeV、1.0 MeV和1.5 MeV单能中子诱发235U裂变的产物产额绝对测量北大核心CSCD

235U的裂变产物产额是核能应用和核物理研究中的重要基础数据。本工作应用高纯锗γ能谱法绝对测量了0.57、1.0 MeV和1.5 MeV中子诱发235U裂变的各能量点30个质量链的产额数据。样品的裂变率通过双裂变室监测,并利用蒙特卡罗(MCNP)模拟了辐照时样品的中子能谱,结果与国际上相应能量点数据在实验不确定度范围内吻合。本工作得到的产额数据澄清了原有数据最高16%的差异并将数据精度从国际上原有数据精度5%~7%提高到3%~5%。     

HDEHP萃取色层法分离测定裂变产物中的铈

一、引言在研究单能中子诱发重核裂变时~(144)Ce产额的工作中,由于中子通量比较低,~(144)Ce放射性很弱,且要求准确测定,因此,这是一种十分精细的工作。整个工作包括三个环节:1)从裂变产物混合物中放化分离~(144)Ce;2)制备成适合测量的源;3)准确测定化学产额。     

The dependence of cumulative ^238U（n,f）fission yield on incident-neutron energy

This work is aim at studying the dependence of fission yields on incident neutron energy,so as to produce evaluated yield sets of the energy dependence.Experimental data at different neutron energies for gas fission products 85m,87,88Kr and 138Xe resulting from the 238U(n,f) reaction are processed using codes AVERAGE for weighed average and ZOTT for simultaneous evaluation.Energy dependence of the cumulative fission product yields on the incident neutron is presented.The evaluated curve of product yield is compared with the results calculated by the TALYS-0.64 code.The present evaluation is consistent with other main libraries in error permission.The fit curve of 87,88Kr can be recommended to predict the unmeasured fission yields.Comparisons of the evaluated energy dependence curves with theoretical calculated results show that the predictions using purely theoretical model for the fission process are not sufficiently accurate and reliable for the calculations of the cumulative fission yields for the 238U(n,f).     

A thin film 10B sample for measuring the atom number

In order to measure differential cross sections of the 10B(n,α)7Li reaction induced by MeV neutrons using the forward-backward coincidence method, a thin film 10B sample was designed and the 10B atom number was determined with a reference 10B film sample. Alpha counts of the 10B(nth,α)7Li reaction from the 10B thin film and the reference sample were measured using a gridded ionization chamber and thermal neutrons, which were moderated and thermalized by paraffin from fast neutrons produced in D(d,n)3He reaction on a 4.5 MV Van de Graaff. The neutron flux was normalized by measuring the fission yield of a small 238U fission chamber.     

MEASUREMENT OF PROMPT NEUTRON SPECTRA OF ^238U FISSION INDUCED BY 10.17 AND 12.12 MeV NEUTRONS

Experimental method to measure the prompt neutron spectra of 238U fission induced by fast neutrons has been developed at HI-13 Tandem Van de Graaff Accelerator Laboratory of CIAE.These techniques employ a multi-segment fission chamber and two liquid scintillator neutron detectors.TOF(time of flight)techniques are used for primary neutrons to select the fission events induced by monoenergetic neutron from 2H(d,n) reactions instead of breakup neutrons from 2H(d,np) reactions.The fission neutron TOF spectra are measured in coincidence with the fission fragments to distinguish fission neutrons from other secondary neutrons.The method permits measurements to a fairly good accuracy under large neutron and gamma ray background.The techniques are described and experimental spectra are presented.     

Relative yield of delayed neutrons and half-life of their precursor nuclei from <Superscript>238</Superscript>U fission by 14.2–17.9 MeV neutrons

The energy dependence of the relative yield of delayed neutrons and half-life of their precursor nuclei from ²³⁸U fission by 14.2–17.9 MeV neutrons is measured. In addition, the detector-blocking effect, which is due to the exposure of the detector to intense fluxes of high-energy neutrons, and the effect of the secondary neutron source D(d, n)³He, a reaction which occurs when a T(d, n)⁴He based neutron source is used, are investigated experimentally and taken into account in the data analysis. The data are analyzed in terms of the average half-life < T> of the precursor nuclei of the delayed neutrons. It is shown that the observed increase of <T> with increasing primary-neutron energy in the energy range studied is predominantly due to the opening of emissive nuclear fission channels. The energy dependence of the average half-life of the delayed-neutron precursors can be described on the basis of the model of emissive fission of three nuclei that fission in this energy range − ²³⁷U*, ²³⁸U*, and ²³⁹U*. __________ Translated from Atomnaya énergiya, Vol. 102, No. 2, pp. 124–132, February, 2007.     

Geant4 simulation of 238U(n,f) reaction induced by D-T neutron source

Knowledge of actinides(n,f) fission process induced by neutron is of importance in the field of nuclear power and nuclear engineering,especially for reactor applications.In this work,fission characteristics of~(238)U(n,f) reaction induced by D-T neutron source were simulated with Geant4 code from multiple perspectives,including the fission production yields,total nubar,kinetic energy distribution,fission neutron spectrum and cumulative γ-ray spectrum of the fission products.The simulation results agree well with the experimental nuclear reaction data(EXFOR) and evaluated nuclear data(ENDF).Mainly,this work was to examine the rationality of the parametric nuclear fission model in Geant4 and to direct our future experimental measurements for the cumulative fission yields of ~(238)U(n,f) reaction.     

Interpretation of delayed neutron phenomena

The Bohr-Wheeler mechanism of delayed neutron emission has been used, together with recent fission mass- and charge-distribution data, to interpret the observed characteristics of delayed neutrons from fission. This interpretation accounts satisfactorily for recently measured periods and relative abundances of the delayed neutrons from six fissionable nuclides: U²³³' U²³⁶, U²³⁸, Pu²³⁹, Pu²⁴⁰, and Th²³². A set of selection criteria are developed which lead to prediction of the “most probable” main precursors as well as possible contributors for each delayed neutron group. Assuming the most probable set of delayed neutron precursors, total delayed neutron yields have been calculated for each of the six fissionable nuclides studied. These calculated yields are in agreement with experiment, thus providing a reasonable explanation of the striking variation in observed total delayed neutron yields, which increase by an order of magnitude from Pu²³⁹ to Th²³² fission. Throughout the analysis, special attention is given to the dominant role of closed-shell effects in delayed neutron systematics.     

Prompt fission neutron multiplicity and spectrum evaluations for n+238U reaction

The prompt fission neutron multiplicity and spectra for n+²³⁸U reaction are calculated using an improved Los Alamos model which includes the linear relation between the average prompt gamma ray energy and the prompt neutron multiplicity and also the average fission fragment kinetic energy dependence on the incident neutron energy. The coefficients describing the quadratic variation of the fission fragment kinetic energy versus the incident energy are obtained by extrapolation of the data and procedure used for n+²³⁵U reaction. The inverse process compound nucleus cross-section of the fissioning nucleus is calculated using the coupled channel method. In the incident energy range where only the first fission chance is involved the comparison of present spectrum evaluation with spectrum calculation using multi-modal model is made too. The calculated prompt neutron multiplicity and spectra of ²³⁸U neutron induced fission are in good agreement with the experimental data for the entire incident energy range required in evaluations, proving the validity of the used procedure.     

用于CSNS反角白光中子能谱及注量率测量的快裂变室

即将建成的中国散裂中子源(China Spallation Neutron Source,CSNS)反角白光中子束线可为核数据测量提供高注量率的脉冲白光中子束流,填补我国核数据测量用白光中子源的空白,提高我国核数据测量水平,满足核能、核技术及基础核物理研究对核数据的需求。该束线建成后,其中子能谱及注量率的精确测量将是开展其它物理实验的基础,快裂变电离室因其独特优点被选为中子能谱和注量率测量探测器。通过实验研究了快裂变电离室的粒子分辨性能、时间分辨性能;确定阴、阳极的合理间距为10 mm,据此测得电离室的时间分辨约15 ns;利用235U样品量计算的探测效率与利用伴随粒子法给出的探测效率在不确定度范围内符合,因此可以标定快裂变室的探测效率。通过这些工作,完成了满足反角白光中子束能谱及注量率测量需求的快裂变室的物理设计。     

Existence of the fifth unstable nuclided series

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