关于~(176)Lu的热中子俘获截面

在测定由(n,γ)反应产生的一些放射性核素的生成率之间的比值时,发现以下情况。用~(177)Lu的生成率B_i~0和~(176)Lu的热中子俘获截面文献值σ_i计算得出的表观中子通量I_i与用~(51)Cr、~(46)Sc、~(59)Fe与~(141)Ce等的生成率和产生它们的热中子俘获反应的截面文献值计算得到的表观中子通量的平均值I_j之比值R_(ij)(平均的中子活化R矩阵元)不是预期的1,而是2.82。     

29—1100keV能区75As中子俘获截面测量

用活化法相对于Au的中子俘获截面，测量了29－1100keV能区^75As(n, γ）^76As的反应截面，测量精度为6．7－7．8％，并将测量结果与现有的实验数据作了比较。     

单晶硅热中子全截面的测量

一、前言从反应堆水平孔道出来的热中子束,伴随着强的γ射线和快中子,这些γ射线和快中子是各种谱仪的本底计数和工作场所的辐射剂量的主要来源,为此,常采用晶体过滤器等加以控制和消除。而决定晶体材料过滤特性的主要参数是晶体的全截面。对于单晶硅,最早由Brugger测定了25,50和70 meV三个能量点的全截面,并拟合成一条能量从几     

^152Sm的22—1019keV能区中子俘获截面的测量

在４．５ＭｅＶ静电加速器上，利用＾７Ｌｉ（ｐ，ｎ）＾７Ｂｅ和Ｔ（ｐ，ｎ）＾３Ｈｅ反应作为中子源，在２２－１０１９ｋｅＶ中子能区以＾１９７Ａｕ的中子俘获截面为标准，用活化法测量了＾１５２Ｓｍ的中子俘获截面，其误差小于６．８％。     

7 ^135Cs热中子活化截面测量

长寿命裂变产物核素的热中子反应截面是重要的核参数，它的深入研究和测量不仅对核结构研究有理论意义，而且对放射性废物的分离嬗变、中子活化分析等方面也有应用价值。     

~（152）Sm的22－1019keV能区中子俘获截面的测量

在４．５ＭｅＶ静电加速器上．利用７Ｌｉ（ｐ，ｎ）７Ｂｅ和Ｔ（ｐ．ｎ）３Ｈｅ反应作为中子源，在２２－１０１９ｋｅＶ中子能区以（１９７）Ａｕ的中子俘获截面为标准，用活化法测量了（１５２）Ｓｍ的中子俘获截面．其误差小于６．８％。     

热中子俘获瞬发γ射线强度计算

简要介绍了热中子俘获发γ射线强度的计算方法,并以实例进行说明,还给出了有关物理自洽检验的方法及其讨论。     

超钚核素的热中子截面评价

超钚核素包括原子序数比钚(Z=94)大的那些元素的各种同位素,即镅及其以上各元素的各种同位素。但目前有中子截面数据的只到~(257)Fm。本评价对~(241)Am直到~(257)Fm的25个核素的热中子截面数据进行了收集、分析和必要的处理,给出了推荐值。数据是按CINDA-A(1935—1976)和CINDA-81(1977—1981.4.1)所列资料目录收集的,凡是     

一台测量快中子辐射俘获截面的大液体闪烁探测器

为了测量快中子辐射俘获截面,我们研制了一台测量γ射线的球形液体闪烁探测器,其直径为1m,容积680l。该探测器属4π几何类型,探测器效率达80％以上。为了降低本底,除了用10cm厚的铅和40cm厚的石蜡建成屏蔽室外,还采用符合方法,使本底计数小于100cps。探测器已经在2.5MeV脉冲质子静电加速器上测量了金、钽和铥等元素的辐射俘获截面。     

Measurement of Effective Capture Cross Section of Americium-243 for Thermal Neutrons

The effective capture cross section of ²⁴³Am for thermal neutrons was measured with an activation method. A sample of ²⁴³Am was irradiated for 10 hrs at Kyoto University Reactor, KUR. After the irradiation, the sample was cooled for one month. In the cooling time, ^244mAm and ^244gAm produced by the irradiation decayed out to ²⁴⁴Cm. The α rays emitted from ²⁴³Am and ²⁴⁴Cm were measured with a silicon surface barrier detector. The neutron flux at the irradiation position was monitored using Au/Al and Co/Al wires. The effective capture cross section was deduced as 174.5±5.3b from the α-ray counts and the neutron flux. The quantity r√T/T₀ in Westcott's convention was 0.037±0.004. The present result was compared with the effective capture cross sections from the JENDL-3.3 and the Mughabghab evaluations.     

Reactor Neutron Capture Cross Section of 60.3-day 124Sb

The radioactive nuclides ¹²⁴Sb (T _1/2=60.3d) and ¹²⁵Sb (T_1/2=2.77yr) were produced from natural antimony by JRR-3 reactor irradiation of 283.5 h through the single and double capture processes. After cooling of 3.50 yr, the γ-ray spectrum of the antimony sample irradiated was measured by a 50 cc coaxial type Ge(Li) detector, and the photo-peak yield ratio of ¹²⁵Sb (E _r=428keV) to ¹²⁴Sb (E _r=1.691 MeV) was obtained. By using a relation between this photo-peak yield ratio and the ¹²⁴Sb (n, γ) ¹²⁶Sb cross section, the reactor neutron capture cross section of 60.3-day ¹²⁴Sb was obtained as 17.4:5:^+2.8 _?2.5b. The thermal neutron flux at the position of antimony sample irradiated was estimated as (4.92±0.38) ×10¹²n/cm²·s by measuring the 1.333-MeV photo-peak yield of ⁶⁰Co, which was activated by reactor irradiation of cobalt impurity contained in the antimony sample.     

Measurements of Neutron Capture Cross Section of 237Np for Fast Neutrons

The neutron capture cross section of ²³⁷Np has been measured for fast neutrons supplied at the center of the core in the Yayoi reactor. The activation method was used for the measurement, in which the amount of the product ²³⁸Np was determined by γ-ray spectroscopy using a Ge detector. The neutron flux at the center of the core calculated by the Monte Carlo simulation code MCNP was renormalized by using the activity of a gold activation foil irradiated simultaneously. The new convention is proposed in this paper to make possible a definite comparison of the integral measurement by the activation method using fast reactor neutrons with differential measurements using accelerator-based neutrons. “Representative neutron energy” is defined in the convention at which the cross section deduced by the activation measurement has a high sensitivity. The capture cross section of ²³⁷Np corresponding to the representative neutron energy was deduced as 0:80 ± 0:04b at 214 ± 9 keV from the measured reaction rate and the energy dependence of the cross section in the nuclear data library ENDF/B-VII.0. The deduced cross section of ²³⁷Np at the representative neutron energy agrees with the evaluated data of ENDF/B-VII.0, but is 15% higher than that of JENDL-3.3 and 13% higher than that of JENDL/AC-2008.     

Neutron Capture Cross Section Measurement of Praseodymium in the Energy Region from 0.003 eV to 140 keV

The neutron capture cross section of praseodymium (¹⁴¹Pr) has been measured relative to the ¹⁰B(n,αγ) standard cross section in the energy region from 0.003 eV to 140 keV by the neutron time-of-flight (TOF) method with a 46-MeV electron linear accelerator (linac) of the Research Reactor Institute, Kyoto University (KURRI). An assembly of Bi₄Ge₃O₁₂ (BGO) scintillators was used for the capture cross section measurement. In addition, the thermal neutron cross section (2,200 m/s value) of the ¹⁴¹Pr(n, γ)¹⁴²Pr reaction has been also measured by an activation method at the heavy water thermal neutron facility of the Kyoto University Reactor (KUR). The thermal neutron flux was monitored with the ¹⁹⁷Au(n, γ)¹⁹⁸Au standard cross section. The above TOF measurement has been normalized to the current activation data (11.6±1.3 b) at 0.0253 eV.

The evaluated data in JENDL-3.3, ENDF/B-VI, and JEF-2.2 have been in general agreement with the current result, except that the JENDL-3.3 and the JEF-2.2 values are clearly lower than the measurement in the cross section minimum region from about 10 to 500 eV.     

热能点裂变截面系统规律

为建立缺乏实验测量数据的热能点裂变截面的评价方法和手段,本文从裂变理论基本公式出发,提出了其系统学公式的基本形式。在推荐热能点裂变截面以及单峰裂变位垒高度的基础上,研究了热能点裂变截面与鞍点态激发能之间的关系,发现了核素的热能点裂变截面与激发能之间的对数关系,通过拟合得到了质子数Z对应的系统学参数。进一步研究这些参数随Z的变化规律,发现了参数与Z的奇偶的关系,并通过拟合建立了全局的系统学公式。研究结果表明,热能点裂变截面与Z相关。     

Emission Probabilities of Gamma Rays from the Decay of 233Pa and 238Np,and the Thermal Neutron Capture Cross Section of 237Np

In order to determine the thermal neutron capture cross section of ²³⁷Np, the relevant γ emission probabilities of the 312-keV γ-ray from the decay of ²³³Pa and the 984-keV γ-ray from the decay of ²³⁸Np are deduced from the ratio of the emission rate to the activity. The emission rate and activity are measured with a Ge detector and a Si detector, respectively. The measured emission probability for 312-keV γ-ray is 41.6±0.9% and that for 984-keV γ-ray is 25.2±0.5%. The emission probabilities are used to correct the thermal neutron capture cross section of ²³⁷Np reported previously, and gives 168±6b. The neutron capture cross section is also determined as 169±6b by α-ray spectroscopic method. The measured emission probabilities and capture cross section are compared with others from references. By averaging these values deduced by different methods, the value of 169±4b is recommended as the thermal neutron capture cross section of ²³⁷Np for 2,200 m/s neutrons.     

Thermal-Neutron Capture Cross Section and Resonance Integral of Americium-241

The thermal-neutron capture cross section (σ_0;g) and the resonance integral (I _0,g) leading to the ground state of 242Am were measured by an activation method for neutron capture by²⁴¹ Am. A method with gadolinium, which was similar to the cadmium difference method, was used to measure the cross section σ_0;g with attention to resonances of²⁴¹ Am. Americium chloride samples containing²⁴¹ Am radioisotope were irradiated for 68 h in the long-irradiation plug of the Kyoto University Research Reactor, KUR. Wires of Co/Al and Au/Al alloys were used as monitors to determine thermal-neutron fluxes and epithermal Westcott's indexes at the irradiation positions. An α-ray spectrometer was used to measure the activity ratios of²⁴² Cm to²⁴¹ Am. On the basis of Westcott's convention, the σ_0;g and I _0,g values were determined as 628 ± 22 b and 3:5 ± 0:3 kb, respectively.