铀钚中子裂变质量分布半经验公式的参数

一、引言对于铀钚中子裂变质量链产额随入射中子能量的变化,已积累了一些数据,Moriyama和Ohnishi(以下简称MO)提出了一个系统学公式,但是对铀钚同位素误差较大。Cook等人做了类似的工作,也还有值得改进的地方。本文用他们的公式拟合了~(235)U,~(238)U和~(239)Pu的实验编评数据,给出了新的参数,精确度有所提高,为进一步的改进提供了基础。     

Theoretical calculation and evaluation of n +~(240,242,244)Pu reactions

The nuclear data of n+~(240;242;244)Pu reactions for incident energy below 200 MeV are calculated and evaluated to meet the requirement in the design of an accelerator-driven subcritical system. The optical model is used to calculate the total, nonelastic, shape elastic cross sections, shape elastic scattering angular distributions, and transmission coefficients. The distorted-wave Born approximation is applied to calculate the direct inelastic scatterings to the discrete excited states. The nuclear reaction statistical models and fission theory are applied to describe neutron, proton, deuteron, triton, helium-3, alpha and c emissions, and fission consistently. The results thus obtained are compared with experimental data and the evaluated data obtained from ENDF/B-VII.1 and JENDL-4.0.     

Energy Dependence of Plutonium Fission-Product Yields

A method is developed for interpolating between and/or extrapolating from two pre-neutron-emission first-chance mass-asymmetric fission-product yield curves. Measured ²⁴⁰Pu spontaneous fission and thermal-neutron-induced fission of ²³⁹Pu fission-product yields (FPY) are extrapolated to give predictions for the energy dependence of the n + ²³⁹Pu FPY for incident neutron energies from 0 to 16 MeV. After the inclusion of corrections associated with mass-symmetric fission, prompt-neutron emission, and multi-chance fission, model calculated FPY are compared to data and the ENDF/B-VII.1 evaluation. The ability of the model to reproduce the energy dependence of the ENDF/B-VII.1 evaluation suggests that plutonium fission mass distributions are not locked in near the fission barrier region, but are instead determined by the temperature and nuclear potential-energy surface at larger deformation.     

人体尸解组织~(239+240)Pu含量的测定

本文用放化分离、半导体α谱仪测量的方法,分析测定了日本北部新潟县1986和1988年死亡居民尸解组织(包括骨骼)中~(239+240)Pu的含量。测定结果表明,胸骨、肝、肺、脾、肾和肌肉中~(239+240)Pu含量的均值分别为5.9、15.4、5.1、1.69、0.33和0.31mBq/kg(鲜重),其中位值分别为5.1、13.0、4.4、1.7、0.27和0.32mBq/kg(鲜重)。     

Improved Los Alamos model applied to the neutron induced fission of 239Pu and 240Pu and to the spontaneous fission of Pu isotopes

The Los Alamos model with multiple fission chances upgraded with (a) the linear relation between the average prompt gamma ray energy and the average prompt neutron multiplicity and (b) the dependence of the average fission fragment kinetic energy on the incident neutron energy, is used for the n+²³⁹Pu and n+²⁴⁰Pu reactions, and also for the spontaneous fission of ^237–241Pu isotopes. In the case of ²⁴⁰Pu fissioning nucleus the variation of the average energy released versus the incident neutron energy is also taken into account. The calculated prompt fission neutron spectra and average prompt neutron multiplicity well represent the experimental data, proving a better predictive power of the improved Los Alamos model.     

Summation calculations of fission-product decay heat, their uncertainties and their applications to a fast breeder reactor

Prediction of unmeasured fission parameters is described concerning mass yields of fission products, average total kinetic energies of fission fragments and average numbers of prompt neutrons in neutron-induced fission of several nuclides related to nuclear reactors. Reliability of predicting unmeasured mass yields of the products from measured mass yields of the primary fragments is discussed. The predicted values of the mass yields of the products are presented for the fissions of ^233,235U, ^239,241Pu by thermal neutrons, of ²³²Th by 1.38-MeV neutrons and of ²³¹Pa, ²³⁸U and ²³⁷Np by fission-spectrum neutrons.A semi-empirical method based on the statistical theory of nuclear fission is extended to unmeasured distributions of the fragments. The mass yields of the products, the average total kinetic energies of the fragments and the average numbers of prompt neutrons are predicted for the fissions of ²³²U and ²³⁸Pu by thermal neutrons, and of ^234,236U, ²⁴⁰Pu and ²⁴²Pu by 2-MeV neutrons. Errors in the predicted values are also discussed.     

Measurement of Fast Neutron Induced Fission Cross Section Ratios of Pu-240 and Pu-242 Relative to U-235

Fission cross section ratios of ²⁴⁰Pu and ²⁴²Pu relative to ²³⁵U were measured by using the 4.5 MV Dynamitron accelerator of Tohoku University. The measurement using mono-energetic neutrons was performed in the neutron energy range of 0.6–7 MeV with the time-of-flight method. Prior to the measurement, a fast timing back-to-back fission chamber was developed with good time resolution to reduce the backgrounds due to α-particles and spontaneous fissions. Furthermore, we took account of the effect of the nonuniformity of fission sample thickness for accurate determination of fission cross section ratio. The uncertainty was estimated by analyzing the correlation between the error sources. The correlation matrix between the measured data was given. The overall uncertainty of the present results is about 2%. For both nuclides, the present results agree well with those by Meadows and by Kuprijanov et al. The JENDL-3 evaluation generally has good agreement with the present results. However, the evaluated data are slightly higher around 1 MeV and lower above 6 MeV than the present results.     

239Pu(nth,f)短寿命裂变产物产额测量

采用γ能谱相对测量方法,以97Zr为内标参考核素,完成了239Pu(nth,f)短寿命裂变产物88 Rb、95 Y、101 Mo、101 Tc、138 Csg、142 La等核素的累积产额测量。实验测得88 Rb、95 Y、101 Mo、101 Tc、138 Csg、142 La的累积产额数据分别为(1.32±0.05)%、(4.69±0.22)%、(6.13±0.32)%、(6.10±0.22)%、(6.24±0.24)%、(4.74±0.17)%。对高纯锗探测器中高能端效率刻度、样品封装与辐照、γ谱测量几何条件设计、γ谱测量与数据分析进行了研究。实验测量裂变产物核素分别位于非对称裂变质量分布双驼峰曲线轻峰的左侧、中部和右侧,重峰的中部与右侧。     

Simple Estimation of Fission Yields with Selective Channel Scission Model

The mass distributions of fission yields for neutron-induced fissions of ²³³U, ²³⁶U, ²³⁸U, ²³⁷Np, ²⁴⁰Pu, and ²⁴²Pu, spontaneous fissions of²⁴¹Am and ²⁴³Am, and fissions of ¹⁰⁶Pd and ¹⁹⁷Au were calculated by the selective channel scission (SCS) model with simple assumptions. The channel-dependent fission barriers were deduced by using shapes of fission fragments in the ground states. The present method makes it possible to estimate fission yields for a wide range of fissionable nuclei without adjustable parameters, although there exist discrepancies between the fission yields calculated by the SCS model and the data of JENDL-3.3 in the mass regions of A = 80–95 and A = 135–150.     

α放射性比的测定方法

采用了3种α放射性比的测定方法:几何级数法、外推法和曲线拟合法。检验了几何级数法的可靠性。把外推法、曲线拟合法的结果与几何级数法的结果作了比较。     

Statistical Estimation of Distributions of Physical Quantities in Nuclear Fission

Making use of a model based on the statistical theory, calculations were performed to obtain the mass yields, the most probable charges, the kinetic energies and the prompt neutron yields of fission fragments, and the mass yields of fission products from thermal-neutron-induced fission of ²³³U, ²³⁵U, ²³⁹Pu, ²⁴¹Pu and from the spontaneous fission of ²⁵²Cf. The calculations are further extended to fast-neutron-induced fission. The scission-point distance is treated as a parameter varying with the mass number of the heavy fragments of fission. This proved successful in approaching the calculated curves closer to the observed values.

It is possible to predict unknown physical quantities in nuclear fission with use made of the method developed in the present work.     

Model-based cross section calculations on production of ~(43,34)Sc,~(45)Ti,~(51)Cr,~(54)Mn,and ~(55)Fe radioisotopes

A cross section database on excitation functions of reactions produced by charged particles is essential for many areas of nuclear research. Particularly, accurate knowledge on nuclear cross sections for the cyclotron production of radioisotopes is very important for nuclear medicine. In the present paper, the cross section calculations for the production of~(43),~(34)Sc,~(45)Ti,~(51)Cr,~(54)Mn, and~(55) Fe radioisotopes were carried out by the use of ALICE/ASH code using the Fermi gas model, Kataria Ramamurthy Fermi gas model, and superfluid nuclear model for nuclear level density. Thereby, these model calculations were compared with the available measured data.     

Approach for the fission fragment total kinetic energy TKE(A) calculation: Application to prompt neutron emission models

A simple approach for the calculation of the fission fragment total kinetic energy, TKE(A), based on the electrostatic repulsion between the fragments connected by a neck in the pre-scission configuration is described. The calculated TKE(A) is obtained in good agreement with the experimental data for many fissioning systems, such as ^233,235U(n_th, f), ²³⁹Pu(n_th, f), ²³⁷Np(n, f), ²⁴²Pu(SF), with minor adjustment of only one parameter. Due to the fact that the present approach can provide with enough trust TKE(A) distributions for fissioning systems for which experimental TKE(A) data do not exist, the possibilities to use the refined Point by Point model of prompt neutron emission can be considerably extended.     

我国膳食中~(90)Sr、~(137)Cs、~(226)Ra、~(228)Ra、~(210)Pb 和~(210)Po含量及其所致内照射剂量

作为1990年全国总膳食调查的放射性物质部分,本文报道了组成我国膳食的各类食品中~(90)Sr、~(137)Cs、~(226)Ra、~(228)Ra、~(210)Pb 和~(210)Po 含量的测定结果;按调查所得膳食组成和食品中核素含量,估算了我国居民(成年男子)当前这些核素经食入所致年摄入量和待积有效剂量当量。结果表明,每年食入所致总待积有效剂量当量约为0.24 mSv,贡献较大的食品是蔬菜、水产品和谷类,贡献较大的核素为~(210)Pb、~(210)Po 和~(228)Ra。这些结果更新了我国膳食中这些核素的资料,补充了来自饮水的数据。文中还讨论了我国膳食组成的地区差异及其对居民摄入量和所致内照射剂量的影响。     

First-chance fission probability and presaddle nuclear dissipation

Dissipation retards fission, resulting in a drop in the first-chance fission probability of a fissioning nucleus with respect to its statistical model value. We use the Langevin model to compute the evolution of the drop(due to friction), P_(f0)~(drop), for the fissioning systems~(220)Th and ~(240)Cf with the presaddle friction strength(b). The firstchance fission probability is shown to depend sensitively on b, and the sensitivity is apparently greater than that of the total fission probability. We further find that although the total fission probability of heavy ~(240)Cf is insensitive to b, its first-chance fission probability is quite sensitive to b.These results suggest that, to strongly limit the presaddle friction strength, an optimal experimental avenue is to measure the first-chance fission probability of heavy fissioning nuclei.     

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。     

^89Sr和^90Sr的同时定量测定

一、引言关于多组份的β源的同时定量测定,Biller曾提出用跟踪测量-图解法获得各组份的量,但是对于寿命较长的~(89)Sr和~(90)Sr-~(90)Y的测量则不适用。为了测量它们,一般采用选择适当的冷却和测量时间,使多组份β源简化为单组份的贡献。所以,有关~(89)Sr和~(90)Sr的同时定量测定尚未见文献中报道。~(90)Sr的半衰期较长(T_(1/2)=28.6a),其子体~(90)Y的β射线能量较高(2.284 MeV),是极毒物质。通过~(235)U裂变生产的口服或注射用的医用同位素(如~(99)Mo-~(99)Tc发生器)中的~(89)Sr和~(90)Sr的含量必须符合我国卫生部部颁标准(~(89)Sr为6×10~(-5)%,~(90)Sr为6×10~(-6)%)。这就需要有一个合适的定量测量方法。为此,本工作研究和建立了β发射核~(89)Sr,~(89)Sr-~(90)Y的分离和同时定量测定的方法。     

Improvements in the description of the multiplicities of the prompt neutrons emitted in fission

Various parameterizations of the multiplicity distribution of prompt neutrons from nuclear fission are investigated. The currently accepted formalism is found to fail for those fission processes which release on average a low number of neutrons. Based on realistic assumptions regarding binary fission, an improved multiplicity distribution formula gives much better agreement with the experimental data. Explicit details of the practical usage of the new formalism are presented. Finally, it is shown that for spontaneously fissioning isotopes, it is possible to calculate the variance of the neutron multiplicity distribution from a knowledge of the mass yield and the variances of the neutron multiplicity distributions of the individual fission fragments.     

中国评价库CENDL-3的宏观检验现状(英文)

CENDL-3是中国评价库CENDL的最新版本,通过采用群常数制作程序系统NJOY及反应堆栅元计算程序WIMSD5A和蒙特卡罗程序MCNP对CENDL-3库进行了包括热堆和快堆的基准装置的检验计算,并将检验结果与实验结果和其它库的计算结果进行了比较和分析。表明CENDL-3库中铀同位素的检验结果是相当不错的;由于裂变谱的改进,钚同位素的检验结果也有了相当好的改进;尽管9Be的检验结果有了明显改进,但计算的keff与其它库相比仍有点偏低。