蒸发和激子模型的(n,a)激发函数系统学研究

(n,a)反应截面对于反应堆,特别是对快堆和聚变堆工程设计是一种很重要的数据。在一些近似条件下,基于核反应蒸发和预平衡激子模型理论研究了入射能量小于 20 MeV的(n,a)激发函数。在靶核30≤A≤209 范围内,基于(n,a)反应的截面实验数据对得到的半经验公式的参数进行了研究,得到了参数对靶核的 N 和 Z 以及中子入射能量的依赖关系。利用普适参数预言(n,a)反应的激发函数,预言值在其误差范围内与实验数据一致。     

~(89)Y(n,2n)~(88)Y反应截面测量

利用活化法的基本原理和相对测量方法,测量得到13.5～14.8MeV的D-T中子作用下的89Y(n,2n)88Y反应截面。89Y(n,2n)88Y反应截面为629～1053mb,相对不确定度为1.7%。并与采用大液闪测量的实验结果和ENDF/B-6库的截面数据进行了比较,当中子能量为14.1MeV处ENDF/B-6数据与实验值的比值为0.99。     

~(107)Ag(d,2n)~(107)Cd和~(109)Ag(d,2n)~(109)Cd反应的激发函数

用13.4MeV的氘束轰击天然银迭靶,银箔前后用铝箔作捕集减能膜。实验确定了~(107)Ag(d,2n)~(107)Cd和~(109)Ag(d,2n)~(109)Cd反应的激发函数,同时作了理论计算。由结果可见,实验值与理论值吻合得很好。     

~(182)W(n,n′α)~(178)Hf~(m2)反应截面研究

对当前有关182W(n,n′α)178Hfm2反应截面的实验测量值和理论计算值相差100倍这一分歧进行了样品成分活化分析和仔细的理论分析。所得结果排除了实验所用样品存在Hf杂质影响这一推论。理论和实验值的分歧依然存在,可能原因是现有的理论计算程序还不能对高角动量激发态进行很好的理论预言     

蒸发和激子模型的(n,α)激发函数系统学研究

(n，α)反应截面对于反应堆，特别是对快堆和聚变堆工程设计是一种很重要的数据。在一些近似条件下，基于核反应蒸发和预平衡激子模型理论研究了入射能量小于20MeV的(n，α)激发函数。在靶核30≤A≤209范围内，基于(n，α)反应的截面实验数据对得到的半经验公式的参数进行了研究，得到了参数对靶核的N和Z以及中子入射能量的依赖关系。利用普适参数预言(n，α)反应的激发函数，预言值在其误差范围内与实验数据一致。     

基于神经网络和决策树算法的裂变产物核(n,2n)反应截面研究

为了大规模预言缺少实验测量的裂变产物核反应截面数据,在整理现有(n, 2n)反应截面5 294个实验数据的基础上,分析相关的物理特征建立实验数据集,分别构建和训练反向传播神经网络和极致梯度提升树模型学习数据。神经网络的隐藏层包含两个子网络,分别由2层各128个神经元构成。极致梯度提升树模型集成了16棵决策树。结果表明,虽然(n, 2n)反应截面实验测量数据大多集中分布在中子入射能量14 MeV附近,且相互之间存在分歧,本工作机器学习模型均可较好描述反应截面的实验测量数据,具有较好的预言能力,对于缺少实验数据的情况同样与评价数据库基本符合。人工神经网络模型在测试集中预测结果与实验数据平均相对偏差小于10%的数据占比超过85%。机器学习方法能为核数据评价研究提供参考。     

（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。     

一种测定裂变谱中子引起的~(241)Am(n,γ)~(242)Am~(g,m)反应截面的新方法

针对不同评价数据给出的裂变谱中子引起的241Am(n,γ)242Amg,m反应截面存在很大差异的状况,本文提出了一种利用钚材料实验的有关数据推算241Am(n,γ)242Amg,m反应截面的方法,两次实验得到的结果分别为0.506×10-24cm2(4.1%)和0.505×10-24cm2(4.1%)。     

质子入射能量Ep≤100 MeV的(p,n)反应激发函数半经验计算方法

基于核反应的蒸发模型和预平衡激于模型，在靶核质量数为30≤A≤140、质子入射能量Ep≤100MeV范围内，对上述模型理论进行了简化，得到了计算(p，n)反应的激发函数的半经验公式。计算结果与已有实验数据的核索符合很好，同时得到了有关参数的系统学公式。     

THE (n, 2n) CROSS-SECTION FOR Na—23 BETWEEN E_n=13.3—18.5 MeV

The (n,2n) cross- section for ~(23)Na have been measured by the activation method in the energy range of E_n=13.3—18.5 MeV. Monoenergetic neutrons were obtained from T(d,n) ~4He reaction at E_d=2.3 MeV. The induced specific activities were detected by a coincidence counting setup. For comparison, the other measured, evaluated and calculated data from E_n=12—20 MeV are also given.     

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％。     

^176Hf（n,2n）^175Hf和^185Re（n,2n）^184Re^m,g反应截面研究

用中国原子能科学研究院ＨＩ－１３串列加速器,高压倍加器和北京大学４．５ＭＶ静电加速器分别获得能量为１０－１２,１４和１８ＭｅＶ的中子,了＾１７６Ｈｆ（ｎ,２ｎ）和＾１８５Ｒｅ（ｎ,２ｎ）的反应堆面,并与现有的实验数据作了比较,初步搞清了分歧的主要原因和激发函数的走向。     

Formation cross sections of nuclei with (n,2n) reactions

Ｆｏｒｍａｔｉｏｎｃｒｏｓｓｅｃｔｉｏｎｓｏｆｎｕｃｌｅｉｗｉｔｈ（ｎ，２ｎ）ｒｅａｃｔｉｏｎｓＣｈｅｎＸｕｅＳｈｉ，ＸｉｅＫｕａｎＺｈｏｎｇ，ＺｈｏｕＳｈｅｎｇＭｏ，ＹａｎＱｉｎｇＱｕａｎ（ＳｈａｎｇｈａｉＩｎｓｔｉｔｕｔｅｏｆＮｕｃｌｅ...     

Direct neutron spectrum measurement to validate Zr(n,2n) reaction cross-section at 14 MeV

Lithium zirconate, Li₂ZrO₃, is known as a candidate blanket material in a fusion reactor. Various neutronics benchmark experiments for zirconium have thus been carried out so far. According to the independent benchmark studies by two parties, the neutron spectrum calculations show fairly large overestimation for most evaluated nuclear data libraries. However, the reason has not yet been made clear up to now. The author's group expects it would be due to a problem of evaluation for the ^natZr(n,2n) reaction cross-section, because the cross-section measurement is basically not possible with the foil activation method for zirconium isotopes except for ⁹⁰Zr.In the present study, two neutrons emitted from ^natZr(n,2n) reaction have been measured directly to investigate the reason for the above overestimation. The measurement was done with our own special technique of detecting angle-correlated neutrons by the coincidence detection technique and the pencil-beam DT neutron source of FNS, JAEA. Angle-correlated energy differential cross-sections for ^natZr(n,2n) reaction were successfully measured. The obtained total cross-section above the emitted neutron energy of 800 keV was fairly larger than the one evaluated in JENDL-3.3. The total cross-section of ^natZr(n,2n) reaction was estimated by extrapolating the spectrum down to zero energy taking into account the nuclear temperature. The estimated cross-section value with the nuclear temperature of 1 MeV, which is larger than the one adopted in JENDL-3.3, was in acceptable agreement with JENDL-3.3. It is suggested from the result that the disagreement pointed out in the previous benchmark studies may be due to inappropriate nuclear temperature used in the evaluation. Further investigation of the nuclear temperature employed in the nuclear data evaluation should thus be carried out once again.     

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.     

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?..     

186W(d,p)187W和186W(d,2n)186Re反应激发函数评价及厚靶产额计算

考虑特征γ射线分支比、衰变常量和标准截面等修正,对氘引起的核反应¹⁸⁶W(d,p)¹⁸⁷W和¹⁸⁶W(d,2n)¹⁸⁶Re的激发函数进行了研究。收集并分析了这些反应激发函数的实验测量数据,应用数学方法对分析处理后的实验数据进行了拟合。同时,采用TALYS程序对这些激发函数进行了理论计算。经过综合评价,给出了50 MeV以下¹⁸⁶W(d,p)¹⁸⁷W和¹⁸⁶W(d,2n)¹⁸⁶Re反应激发函数的推荐值,利用得到的¹⁸⁶W(d,2n)¹⁸⁶Re激发函数推荐值计算了医用放射性核素¹⁸⁶Re的厚靶产额。     

Evaluation of D（d,n）^3 He reaction neutron source models for BNCT irradiation system design

A mathematical method was developed to calculatc the yield.energy spectrum and angular distribution of neutrons from D(d,n)3 He(D-D)reaction in a thick deuterium-titanium target for incident deuterons in energies lower than 1.0MeV.The data of energy spectrum and angular distribution wefe applied to set up the neutron source model for the beam-shaping-assembly(BSA)design of Boron-Neutron-Capture-Therapy(BNCT)using MCNP-4C code.Three cases of D-D neutron source corresponding to incident deuteron energy of 1000.400 and 150 kaV were investigated.The neutron beam characteristics were compared with the model of a 2.45 MeV mono-energetic and isotropic neutron source using an example BSA designed for BNCT irradiation.The results show significant differences in the neutron beam characteristics,particularly the fast neutron component and fast neutron dose in air,between the non-isotropic neutron source model and the 2.5 MeV mono-energetic and isotropic neutron source model.