(n,2n)和(n,3n)激发函数的计算

本文从入射中子能量为E=14MeV的σ_(n,2n)实验值出发,应用复合核模型,计算了十三种无分支比复合核衰变的非裂变重核(A>169)的(n,2n)、(n,3n)激发函数。与实验激发曲线比较,讨论了计算的合理性和可靠性。     

高气压屏栅电离室的调试和58Ni(n,p)反应双微分截面的试测

介绍了高气压屏栅电离室的结构和调试,并对＾５８Ｎｉ（ｎ,ｐ）试测结果进行了分析,结果证明此电离和测量方法对（ｎ,ｐ）反应的测量是适用的。目前正用此电离室进行测量（ｎ,ｐ）反应堆面的实验。     

14 MeV能区中子引起的58 Ni(n,P)58m+gCo 反应截面测量

用活化法以^27Al(n，α)^24Na反应截面为中子通量标准，对14McV能区中子引起的^58Ni(n,p)^58m gCo反应截面进行了测量。中子能量是用金硅面垒半导体探测器测定的。     

（p,n）反应激发函数的系统学研究

从普朗克黑体辐射公式和实验测量数据出发，提出了１个包含２个可调参量、入射了能量从阈能到１５０ＭｅＶ、靶核质量数在２０〈Ａ〈２３８范围内能够较好描述（ｐ，ｎ）反应激发函数的学经验公式。     

En〉6MeV能区（n,p）反应截面的物理分析

在Ｅｎ〈６ＭｅＶ能区,以＾５８Ｎｉ（ｎ,ｐ）＾５８Ｃｏ和＾６４Ｚｎ（ｎ,ｐ）＾６４Ｃｕ反应为例,对（ｎ,ｐ）反应堆面的实验数据进行物理分析,得出在评价这段能区的反应堆面时更应重视使用＾６Ｌｉ－ｐ和Ｔ－ｐ中子源实验数据的结论。Ｔ     

用聚乙烯薄膜测中子绝对注量率

在测量中快中子（ｎ,ｐ）反应的实验中,同样利用屏栅电离室测得聚乙烯薄膜反冲质子的能谱,并利用蒙特－卡罗方法对其进行校正,则得到中子的绝对注量率,将其结果与＾２３８Ｕ测得的结果进行比较,二者在误差范围内相同,说明用此方法测量中子绝对注量率是可行的。     

人骨中232Th,230Th和228Th含量的测定

本文采用放化分离、电沉积制源、低温半导体α谱仪测量的方法测定了59例正常人(非钍尘作业人员)骨中~(232)Th、~(230)Th 和~(228)Th 的含量。测定结果表明,骨中~(232)Th 和~(228)Th 含量的均值分别为31、23和62 Bq/kg(鲜重),标准差分别为19、18和39 Bq/kg(鲜重),骨中钍所致的平均剂量分别为:~(232)Th,0.031 mrad/a;~(230)Th,0.027 mrad/a ~(228)Th,0.085 mrad/a。骨中~(230)Th 含量与年龄呈相关,吸烟与非吸烟者之间骨中三种钍核素含量差异均不显著。     

Extraction of trace thorium from hydrochloric acid media by 1-phenyl-3-methyl-4-benzoyl-5-pyrazolone

The paper describes the solvent extraction of trace thorium from hydrochloric acid media by 1-phenyl-3-methyl-4-benzoyl-5-pyrazolone (PMBP) using a radioactive tracer technique. The percent extraction of thorium was studied as a function of acidity, PMBP concentration and equilibrium time. The back-extraction behavior of thorium from the organic phase was also tested. Separation of thorium was performed from fission products produced in 14 MeV neutron bombardment of natural uranium by employing the PMBP extraction procedure. The gamma-ray spectra of the separated thorium fractions show that thorium can be separated from most of fission products and a large amount of uranium.     

Measurement of Average Cross Section for 233U(n, 2n)232U Reaction

Isotopically pure ²³³U samples, with only 3 × l0^?3 ppm²³²U content, were prepared by thermal neutron irradiation of thoria and subsequent chemical processing. The ²³³U sample thus obtained was reirradiated with a fission neutron spectrum in the core of the Kyoto University Reactor (KUR), and measurements were made of the fission spectrum average cross section for the ²³³U(n, 2n) ²³²U reaction. A value of 4.08±0.30 mb was obtained for this cross section, in agreement with the renormalized value of Halperin et al. within the limits of experimental error.

In order to assess the energy dependent cross section from the value of this integral measurement, the ²³³U (n, 2n) cross section was calculated assuming a Maxwellian-type fission spectrum and adopting the energy dependent evaluated cross sections of ENDF/B-III and other authors. The values of the cross section thus determined were found to be about 32 to 91% larger than the measured cross section given above. The result of Pearlstein's calculation of the ²³³U(n, 2n) cross section by the statistical model, again assuming the Maxwellian distribution, is smaller than the measured cross section by about 19%.     

Excitation functions of (n,p) reactions for stable isotopes of Cr,Fe and Ni from threshold to 20 MeV

The excitation functions of (n,p) reactions for the stable isotopes of Cr, Fe and Ni were calculated using EMPIRE 3.0 β1 (ARCOLE) from threshold to 20 MeV. The cross-sections are calculated using full featured Hauser–Feshbach statistical model with pre-equilibrium effects by invoking DEGAS option in the code. A good agreement between the calculated and experimental data (EXFOR data base) as well as evaluated data is obtained with option of neutron and proton potentials by Koning (Global) and HFB parity dependent nuclear level density. This is an important step to the validation of nuclear model with superior predictive power. The compound nucleus and pre-equilibrium reaction mechanisms as well as the isotopic effects were also studied.     

Real-time measurement of implanted deuterons by using the nuclear reaction H(d,p)H

We propose a method for real-time measurement of the density of implanted deuterons in solid materials during deuterium implantation. In this method, the density of implanted deuterons is measured by detecting the emitted protons from the deuteron fusion reaction between the incident deuterons and the implanted deuterons. A negative deuterium beam with an energy of 90 keV is used both for the implanted atoms and a probe beam to measure the implanted deuterons. The density of the implanted deuterium atoms was observed to be drastically different between the single crystal and poly-crystal in Ta.     

2H(d,n)3He核反应中子注量的伴随粒子法测量

^2H(d,n)^3He核反应单能中子源广泛应用于MeV中子的散射和极化实验。采用伴随粒子法测量中子注量，用Si半导体探测器测量^3He粒子，用0.8μm Al箔来屏蔽散射的d束，系统可很好地分辨^3He,d,T和p，可测d^ 束能量到165keV，测量结果与用NE213探测器的结果相比较，一致性好于97％。     

35MeV以下56Fe(n,p)56Mn反应截面及协方差评价

56Fe(n,p)56Mn通常作为标准反应来监测中子场通量,该反应截面数据的准确性直接影响到活化法测量结果的精确度,进而影响到实验待测物理量的精度。本文开展了56Fe(n,p)56Mn反应截面实验测量数据评价工作与协方差计算工作,首先系统分析EXFOR中现有的56Fe(n,p)56Mn反应截面实验测量数据,对实验数据进行了归纳总结分析,并从中子源、测量方法、探测器类型等方面对56Fe(n,p)56Mn直接测量实验数据进行评价。然后,拟合给出适用入射中子能量区间为295～35 MeV的激发曲线。随后,针对评价中重点推荐的实验数据开展了关联协方差矩阵的计算工作。最后,使用核反应计算程序TALYS对56Fe(n,p)56Mn激发曲线进行了调参计算并和评价数据进行了比较分析。该工作拓展了现有的中子活化反应截面实验数据的评价方法,结果提高了35 MeV以下中子诱发56Fe(n,p)56Mn反应的评价数据精度。     

闪烁法测量伴随~3He粒子的中子飞行时间谱仪

在D(d,n)~3He反应中,目前常采用Si(Au)面垒型半导体探测器测量伴随粒子。半导体探测器的能量分辨率高,是这种方法的优点,但由于~3He粒子能量低,电荷灵敏前置放大器所给出的~3He信号幅度小,容易受到噪声以及干扰信号的影响,因而谱仪的时间分辨性能不容易做得很好。比如Ohio大学的中子飞行时间谱仪,出射~3He粒子的能量为650     

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.     

无载体186Re的制备

用１６ ＭｅＶ质子轰击１８６Ｗ 同位素靶,经１８６Ｗ（ｐ,ｎ）１８６Ｒｅ 反应生成１８６Ｒｅ。采用酸性Ａｌ２Ｏ３ 柱分离１８６Ｒｅ,并继而通过阴离子交换树脂柱浓缩等处理,得到可供标记用的无载体１８６Ｒｅ的生理盐水溶液。１８６Ｒｅ的总收率约为８５％ ,１８６Ｒｅ 的纯度大于９９．２％ ,１８６Ｒｅ的厚靶产额为１．５９ＴＢｑ／（Ａ·ｈ）,１８６Ｗ 的回收率大于９２％ 。     

Radiation protection of mox-fuel by doping with Pa and U

The paper addresses the problem of MOX-fuel self-protection at the “Spent Fuel Standard” level and more during full cycle of MOX-fuel management. Under conditions of the closed LWR cycle the proliferation-resistance levels were evaluated for fresh and spent MOX-fuel doped with ²³¹Pa and ²³²U. According to the evaluations, it was derived that cyclic regime with Pa-U feeding at the level of 5% HM makes it possible to achieve the proliferation resistance of fresh MOX-fuel at the level high enough to protect it against short-term unauthorized actions (receiving the lethal dose for about 10 minutes in the vicinity of MOX-fuel assembly) and also against the acts of terrorism (receiving the shock lethal dose for a few minutes).     

186W(d,2n)186Re反应制备无载体186Re

１８６Ｒｅ的半衰期为９０．６ｈ,β~－粒子能量中等（最大能量为１．０７ＭｅＶ）,伴随发射可用于显像的１３７ｋｅＶ（９．２％）的γ射线。就核性质而言,１８６Ｒｅ最适宜标记单抗［１］,但遗憾的是,目前市场上可以获得的均为由反应堆生产的有载体中等比活度的１?..     

碳材料反射中子的238U裂变反应率测量和计算

用小型贫化铀裂变室和俘获探测器测量了D-T聚变中子在碳材料反射体上反射中子引起的^238U裂变反应率分布。比较了无碳材料反射体的测量结果。实验测得的^238U裂变反应率合成不确定度为5．1％～6．4％。实验结果与用MCNP／4A程序和ENDF／B-Ⅳ库数据计算的结果在误差范围内符合。