~(71)Ga(n,γ)~(72)Ga和~(180)Hf(n,γ)~(181)Hf反应截面的测量与评价

为解决目前71 Ga(n,γ)72 Ga反应和180 Hf(n,γ)181 Hf反应截面实验数据的分歧,在中国原子能科学研究院的600kV高压倍加器和5SDH-2串列加速器上用活化法在0.5～3MeV能区内测量了这两个反应在4个能点的反应截面。并对国内外0.01～4MeV范围内的实验数据进行了修正和评价,最终给出了这两个反应在此能区范围内的推荐值。     

~(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。     

Cross Section for ~(176)Hf(n,2n)~(175)Hf Reaction

Measurements of neutron cross section of ~(176)Hf(n,2n)~(175)Hf are reported. In the experiment, the D(d,n)~3He and T(d,n)~4He reactions were served as the neutron sources, in neutron energy ranged of 10～12 MeV, about 14 MeV and 18 MeV. The neutron flux was monitored with the ~(93)Nb(n,2n)~(92m)Nb reaction and BF_3 long counter or ~(238)U fission chamber. Details of this experiment were described and the results were compared with ENDF/B-6, JEF-2, JENDL-3, ADL-3 and the data from literature.     

~(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     

14.8 MeV中子诱发78Kr(n,2n)77Kr反应截面的测量

快中子诱发(n,2n)反应截面的测量在核反应机制研究和核技术应用等方面有着广泛的应用价值。本文在中国原子能科学研究院的高压倍加器上,基于活化法实验测量了78Kr(n,2n)77Kr在148 MeV能点的反应截面。样品靶为高纯78Kr气体样品,用十万分之一天平称重得到78Kr的质量,将两片高纯93Nb薄片分别固定在样品靶两侧以监测中子注量率。利用T(d,n)4He反应产生148 MeV中子,轰击距中子源约10 cm的样品靶大于4 h后,用准确刻度过效率的HPGe探测器测量活化产物 77Kr和92Nbm的活度。利用蒙特卡罗程序计算中子注量率修正、样品自吸收修正、样品几何修正等因子,得到了78Kr(n,2n)77Kr的反应截面,并将结果与文献值和评价数据库进行了比较。研究结果有助于提高78Kr(n, 2n)77Kr反应截面测量和评价的水平。     

^179Hf（n,2n）^178Hf^m2和^209Bi（n,2n）^208Bi反应截面的测量

用活化法测量相对于~(93)Nb(n,2n)~(92)Nb~m反应的~(179)Hf(n,2n)~(178)Hf~(m2)的反应截面和相对于~(27)Al(n,2n)~(24)Na反应的~(209)Bi(n,2n)~(208)Bi的反应截面。在中子能量为14.4 MeV处~(179)Hf(n,2n)~(178)Hf~(m2)反应的测量截面为(6.04±0.32)×10~(-31)m~2。在中子能量为14.6 MeV处~(209)Bi(n,2n)~(208)Bi反应的测量截面为(2279±173)×10~(31)m~2。在这些测量中,中子能量是用~(90)Zr(n,2n)~(89)Zr~(m+8)反应和~(93)Nb(n,2n)~(92)Nb~m反应的截面比法测定的。     

~(141)Pr(n,γ)~(142)Pr反应截面的测量

用活化法测量了中子能量在 0.539 MeV,1.090 MeV 和 1.587MeV 的 Pr(n, γ)142Pr 核反应截面值,γ 放射性活度用高纯锗探测 141器测量,实验的测量误差在±(6～7)%范围内。实验结果与其它各家的实验值进行了比较和分析,给出了推荐的激发曲线。     

~(175)Hf的半衰期测量

~(175)Hf现有的半衰期数据偏少且分歧较大,对核参数的准确使用不利。本实验通过加速器质子束流轰击~(175)Lu,并使用HDEHP萃淋树脂进行离子交换,得到无载体无~(181)Hf干扰的高纯度~(175)Hf液体测量源,对其中的杂质~(65)Zn与~(56)Co的去污因子分别为5.2×10~3与2.3×10~3;引入一固定位置的监督源~(137)Cs与~(175)Hf进行了40d的连续测量,对343keV以及661keVγ射线计数率的比值关于测量时间进行线性拟合,得到~(175)Hf的半衰期为(70.73±0.25)d,并对测量结果进行了相关检验。     

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。     

快中子64Zn(n,α)61Ni反应微分截面实验测量

由于64Zn(n,α)61Ni反应的剩余核是稳定的,不能用通常的活化法来测量,致使该反应截面实验数据缺乏.利用双屏栅电离室作为带电粒子探测器,在En=2.54,4.00,5.03,5.50与5.95MeV 5个能点,对64Zn(n,α)61Ni反应的微分截面进行了实验测量,并通过微分截面对角度的积分得到了反应截面.实验在北京大学4.5MV静电加速器上进行.2.54MeV的单能中子采用固体氚-钛靶T(p,n)3He反应产生,其余四种能量的准单能中子通过氘气体靶D(d,n)3He反应获得.绝对中子通量采用238U(n,f)反应来确定,实验过程中用BF3长中子计数器进行相对中子通量监测.测量结果与已有的实验与评价数据进行了比较.     

The cross section for the K(n,p)Ar reaction between 14.2 and 17.2 MeV

Activation techniques have been used to measure the cross section for the ⁴¹K(n,p)⁴¹Ar reaction between 14.2 and 17.2 MeV. Neutrons were produced by the ³H(d,n)⁴He reaction, and the mixed-power method was used to measure the neutron flux through the ²⁷Al(n,)²⁴Na reaction. The activated samples were counted for the 1294 keV, 1.827 h γ-activity of ⁴¹Ar and the 1369 keV, 15.03 h γ-activity of ²⁴Na using a 16% Ge(Li) detector and a 4096-channel analyzer. The cross sections for the ⁴¹K(n,p)⁴¹Ar reaction using the mixed-power method were found to be 53 ± 3 mbarn at 14.2 ± 0.2 MeV, 47 ± 3 mbarn at 15.2 ± 0.2 MeV, 41 ± 3 mbarn at 16.2 ± 0.2 MeV and 36 ± 4 mbarn at 17.2 ± 0.2 MeV. The associated-particle method was also used for measuring the neutron flux in order to check the mixed-powder result at 14.2 MeV. The average cross section for three associated-particle runs at 14.2 MeV was found to be 50 ± 3 mbarn which, within experimental error, agrees with the mixed-powder value.     

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。     

Measurement of the cross sections for the reactions Cr(n,2n)Cr, Zn(n,2n)Zn, Y(n,2n)Y and Zr(n,2n)Zr from 13.5 to 14.8 MeV

Cross section measurements for the reactions ⁵²Cr(n,2n)⁵¹Cr, ⁶⁶Zn(n,2n)⁶⁵Zn, ⁸⁹Y(n,2n)⁸⁸Y and ⁹⁶Zr(n,2n)⁹⁵Zr were carried out in the neutron energy range 13.47–14.79 MeV applying the activation technique. Neutrons were produced via the T(d,n)⁴He reaction, making use of the variation of neutron energy with the emission angle. The neutron fluences incident on the samples were determined relative to the well-evaluated cross section for the reaction ⁹³Nb(n,2n)^92mNb.

The induced γ-ray activities of the irradiated Zn, Zr and Y₂O₃ samples and their monitor foils were measured by means of a calibrated Ge(Li) γ-ray detector at the KFI, Debrecen. At the IRK, Vienna, relative γ-ray measurements using a high-purity Ge detector were combined with integral γ-ray counting by means of a NaI(TI) well-type detector on the Cr, Zn and Zr foils of highest activity and on some Nb monitor foils; integral γ-ray counting only was applied in the case of the Y₂O₃ samples. All necessary corrections were taken into account.

The results are compared to the corresponding results of cross section measurements published in the literature. The uncertainties obtained in this work are considerably smaller in most cases than the uncertainties given by other authors.     

6Li(n,t)4He反应微分截面的实验测量

用屏栅电离室对1．85和2．67MeV中子^6Li(n,t)^4He反应的微分截面及截面进行了测量。使用氚固体靶通过T(p,n)^3He反应产生中子,利用BF3长中子管进行相对中子通量监测,绝对中子通量则用^238U(n,f)反应来刻度。测量结果与已有数据进行了比较。     

The 63Cu(n,2n)62Cu and 65Cu(n,2n)64Cu cross sections at 14.8 MeV

Measurements have been made of the ⁶³Cu(n,2n)⁶²Cu and ⁶⁵Cu(n,2n)⁶⁴Cu cross sections. Separated isotope targets were irradiated with 14.8 MeV neutrons and the resulting ⁶²Cu and ⁶⁴Cu activities were measured using both 4πβ-γ coincidence counting and by counting in coincidence the annihilation radiation produced following the β⁺-decay of ⁶²Cu and ⁶⁴Cu. The variation in the neutron flux and the neutron energy were measured during each single irradiation. Good agreement was obtained for the cross-section values using the two methods. However, the standard deviation of the mean of the ⁶⁵Cu(n,2n)⁶⁴Cu cross-section measurements was significantly greater when the 4πβ-γ coincidence method was used. The measurements were made relative to the ⁵⁶Fe(n,p)⁵⁶Mn cross section. Values of 549 ± 11 and 968 ± 20 mbarn were obtained using a value of 108.5 mbarn for the Fe cross section at 14.8 MeV.     

Activation cross sections and isomeric cross section ratios for the (n,2n) reactions on Lu, Pt and Se from 13.5 to 14.6 MeV

The cross sections for the ¹⁷⁵Lu(n,2n)^174m,gLu, ¹⁹⁸Pt(n,2n)^197m,gPt and ⁸²Se(n,2n)^81m,gSe reactions and their isomeric cross section ratios σ_m/σ_g have been measured in the neutron energy range of 13.5-14.6 MeV using the activation technique. Nuclear model calculations using the code HFTT, which employs the Hauser-Feshbach (statistical model) and exciton model (precompound effects) formalisms, were undertaken to describe the formation of the products. The total cross sections for the (n,2n) reaction on ¹⁷⁵Lu, ¹⁹⁸Pt and ⁸²Se are compared with experimental data found in the literature, with results of published empirical formulae, and with values of model calculations including the pre-equilibrium contribution.     

Measurement of Gamma-Ray Production Cross Sections of Iron for Incident Neutron Energies between 6 and 33 MeV

Measurement of differential γ-ray production cross sections, i.e. (n, x γ) cross sections, of Fe was made for neutron energies from 6 to 33 MeV. Neutrons used in the experiment were white neutrons produced with (p, n) reactions by 35 MeV protons using a thick Be target. The neutron energy was analyzed by the time-of-flight method and bunched into 3 MeV wide energy bins, for each of which the spectrum of secondary γ-rays produced in an Fe sample was measured by a BGO scintillator at an angle of 144° to the neutron beam direction.

The obtained (n, xγ) cross sections agreed well with other data and the evaluated data file of ENDF/B-IV at neutron energies below 15 MeV where data were existing. The JENDL-3 file overestimated the γ-ray spectra at γ-ray energies of 3 to 7 MeV. The present work newly provided the data in the neutron energy range above 20 MeV. The GNASH calculation made by Young reproduced the measured data fairly well even at these higher energies.     

Measurements of activation cross sections for Lu(n, α)Tm,Lu(n, α)Tm and Lu(n, p)Yb reactions induced by neutrons around 14 MeV

The cross sections for the ¹⁷⁵Lu(n, α)¹⁷²Tm, ¹⁷⁶Lu(n, α)¹⁷³Tm and ¹⁷⁵Lu(n, p)^175m+gYb reactions have been measured in the neutron energy range of 13.5–14.8 MeV using the activation technique. The first data for ¹⁷⁵Lu(n, α)¹⁷²Tm reaction cross sections are presented. In our experiment, the fast neutrons were produced via the ³H(d, n)⁴He reaction on K-400 Neutron Generator at Chinese Academy of Engineering Physics (CAEP). Induced gamma activities were measured by a high-resolution (1.69 keV at 1332 keV for ⁶⁰Co) gamma-ray spectrometer with high-purity germanium (HPGe) detector. Measurements were corrected for gamma-ray attenuations, random coincidence (pile-up), dead time and fluctuation of neutron flux. The neutron fluences were determined by the cross section of ⁹³Nb(n, 2n)^92mNb or ²⁷Al(n, α)²⁴Na reactions. The neutron energy in the measurement was by the cross section ratios of ⁹⁰Zr(n, 2n)^89m+gZr and ⁹³Nb(n, 2n)^92mNb reactions. The results were discussed and compared with experimental data found in the literature and with results of published empirical formulae.