基于白光中子源的197Au中子辐射俘获截面测量及共振参数分析

中子辐射俘获反应在反应堆运行、核装置设计及核天体物理研究中起重要的作用. 4πBaF₂探测装置有着高时间分辨能力、低中子灵敏度、高探测效率等优点,适合开展中子辐射俘获反应截面数据的测量.中国原子能科学研究院核数据重点实验室建立了伽马全吸收装置(Gamma total absorption facility, GTAF),该装置用28块六棱BaF₂晶体和12块五棱BaF₂晶体构成了外径25 cm,内径10 cm的球壳,覆盖了95.2%的立体角.利用GTAF在中国散裂中子源Back-n束线上,测量了197Au(n, γ)的反应截面数据.测量数据通过能量筛选、PSD方法、晶体多重性筛选进行了初步本底扣除,随后结合对^natC及空样品的测量数据对本底进行了分析及扣除,获得了197Au俘获反应的产额,利用SAMMY程序拟合得到了¹⁹⁷Au在1—100 e V的共振能量、中子共振宽度和伽马共振宽度参数.实验测量结果与ENDF/B-VIII.0数据库符合良好,其共振参数存在一定差异,分析原因可...     

Gamma全吸收型BaF2探测装置中子屏蔽体与吸收体的研究

中国原子能科学研究院已经建造完成了我国第一套全吸收型BaF₂探测装置,采用瞬发γ测量法,精确测量中子俘获反应截面。中子源是利用HI-13串列加速器产生的脉冲化质子束,通过7Li(p, n)7Be反应建立。为了有效降低周围环境材料和探测器产生的散射中子本底,约束中子束流的形状,使用MCNP程序模拟设计了屏蔽体,采用含硼聚乙烯(B₄C质量分数为5%)包裹5 cm铅的方案,以及准直器采用平行孔的方案。该设计使样品处的中子束斑平整均匀,直径约为2 cm,束斑外的中子注量降低5个数量级,γ注量降低3个数量级。同时设计了中子吸收体(外半径为10 cm,厚度为7 cm)用于吸收待测样品产生的散射中子。MCNP和GEANT4程序的模拟结果表明:选择含硼聚乙烯(10B₄C质量分数为10%)作为中子吸收体的加工材料,其中子吸收率达到了80%,并设置1 MeV的能量加和阈,能够满足在线测量中子俘获反应截面的实验要求。     

不同厚度镥样品中子俘获反应实验研究

C₆D₆闪烁体探测系统结合脉冲权重技术被广泛应用于中子俘获反应截面测量研究.实验中采用的样品厚度直接影响中子束流时间,同时也影响实验数据的可靠性.本文基于中国散裂中子源反角白光束线(CSNS Back-n)C₆D₆探测系统,对比研究了不同厚度的镥(Lu)样品中子俘获反应截面的实验测量.利用GEANT4蒙特卡罗程序模拟了考虑样品厚度的探测系统光响应,计算出精确的脉冲权重函数.实验中,通过采用较长中子飞行距离和本底测量,得到了高精度的共振区产额分布.通过R矩阵理论分析产额分布,得到了相应的实验共振参数.结果发现,较厚Lu样品因其厚度效应导致共振曲线发生变化,实验共振参数与ENDF/B-Ⅷ.0评价数据库差距较大;然而,较薄Lu样品实验结果能够很好地再现ENDF/B-Ⅷ.0评价数据.     

强辐射环境下高能脉冲裂变中子探测方法

在研究通道衰减、探测方法分离和探测器中子/射线本征分辨的基础上,研究了测量高能脉冲裂变中子数目的探测技术。基于电流型Si-PIN探测器,设计了减本底的背靠背探测结构,给出了测量强射线和低能散射中子干扰信号及有效扣除强辐射本底的实现方法,最终实现了高n/n和n/分辨测量和强裂变中子、射线混合场中的高能脉冲裂变中子数目探测,探测系统的信号/辐射本底比可达到10倍以上。     

高能中子消失法的检验

以前在贫化铀／聚乙烯／铁组合球装置上进行的高能中子消失法的检验，存在的问题在于贫化铀内腔太小，距离的微小误差就会对实验结果产生很大影响，实验重复性差。因此用同样是中子增殖材料的铍代替贫化铀作补充实验。这样，一则可以减小因为距离的偏差对实验的影响；二则可能对^197Au(n，γ)、^198Au反应的影响再做研究。用铍／聚乙烯／铁组合球装置，在ns-200加速器上照射，用HPGe探测器测量．Au，Al，Nb高阈能指示剂的活化γ射线，确定它们在装置中的反应燃耗，以此检验高能中子消失法。     

中重核中子辐射俘获γ射线强度函数研究

假设退激过程中除包含巨偶极共振模式外还存在⁶He,⁶Li,⁶Be,⁷Li和⁷Be等粒子集团激发态的退激过程.本文对这一物理假定作了进一步分析.利用据此建立的包括这些过程在内的γ射线强度函数,计算了在核素⁹³Nb,¹⁸¹Ta和天然元素Ag上入射中子能量在0.01—5MeV能区以及在核素¹⁹⁷Au上入射中子能量在0.01—10MeV能区的中子辐射俘获反应截面和γ能谱,得到了与实验数据较好符合的结果.特别是可以较好地解释γ能谱中5.5MeV之后的反常突起.这表明,上述物理假定适用于中重核中子辐射俘获反应.     

元素分离样品中丰中子同位素弱γ活性探测

MPGeγ探测器的γ能量信号与4πΔEβ探测器的β射线能损信号符合后再与BGO探测的β+衰变的正电子湮灭511keV γ信号作反符合组成一种新的探测系统. 该系统可使γ谱测量的康普顿本底下降约一个数量级. 对缺中子同位素衰变γ射线的探测作强抑制的同时,丰中子同位素衰变γ射线的探测仍能保持相对单谱为(46±3)%的高效率. 使用该系统对已被合成的丰中子核素²⁰⁸Hg的半寿命进行了一次新的测定. 所得新的²⁰⁸Hg半寿命测定值41.5+min,与以往用放射化学母牛法给出的结果一致,测量误差有较大改进.     

93Nb(n,2n)92mNb反应截面测量

用活化法以^27Al(n,α)^24Na反应截面为中子注量标准，对14MeV能区中子引起的^93Nb(n,2n)^92mNb反应截面进行了测量。中子能量由硅探测器法测定。     

一种基于~4He气闪烁体的裂变中子探测器

研制了一种新中子探测器,它以²³⁵UO₂裂变靶作为转换靶,⁴He气体作为闪烁体.该探测器充分结合了²³⁵U和⁴He两种核素的特点,从而具有中子能量响应平坦、中子灵敏度较高、n/γ分辨本领高等优点,能很好地在混合脉冲裂变辐射场中测量中子.本文对探测器的原理和结构设计进行了介绍,计算了不同能量中子、γ射线在探测器中的能量沉积,并从理论和实验上对探测器的中子灵敏度、γ射线灵敏度、n/γ分辨本领和时间响应进行了研究.结果表明探测器的中子灵敏度约10^-15C·cm²,γ灵敏度约10^-17C·cm²,时间响应约33.1 ns.     

197Au中子辐射俘获过程中γ射线强度函数与能谱研究

文章假定在复合核首次和级联γ退激过程中，除包含巨偶极共振模式外，还存在^6He,^6Li,^6Be,^7Li和^7Be等粒子集团的激发态的退激过程，并据此建立了包括这些过程的γ射线强度函数，计算了入射中子能量在0．01－3MeV能区的中子辐射俘获反应：197Au(n,γ）的反应截面和γ能谱，得到了与实验数据较好符合的结果，特别是，很好地解释了γ能谱中5．5MeV之后的反常突起。     

锂玻璃探测器中子探测效率的刻度

为了精确测量keV能区的中子俘获截面,中国原子能科学研究院正在建造一台4π 全吸收型γ 探测装置---GTAF,锂玻璃探测器将会作为中子束流监视器测量中子能谱。利用5SDH-2 加速器刻度了锂玻璃探测器在两个入射中子单能点(250 和565 keV) 的探测效率,并使用EANT4 和MCNP 程序模拟计算了锂玻璃探测器的相对探测效率。通过归一化实验数据和模拟结果,得到了锂玻璃探测器在10keV~1 MeV 能区的中子探测效率曲线。对于把锂玻璃探测器测量得到的飞行时间谱转化为中子束流能谱,是一项非常重要的工作,同时为探测器效率刻度提供了新方法。In order to accurately measure the neutron capture cross section in the energy range of keVMeV, 4 πgamma-ray total absorption facility (GTAF) is being constructed at China Institute of Atomic Energy (CIAE). The lithium glass detector will be used as a neutron beam monitor for GTAF. The detection efficiency of the lithium glass detector at two incident neutron energy points (250, 565 keV) was calibrated in 5SDH-2 accelerator, and the relative detection efficiency was simulated by GEANT4 and MCNP code. By the normalization of the experimental data and simulation result, the neutron detection efficiency curve of the lithium glass detector between 10 keV and 1 MeV was obtained. This work will be important to convert the Time-of-flight spectrum that be measured by Li-glass detector to the energy spectrum of neutron beam, and provide the new method for calibration of detection efficiency.     

Neutron capture cross section measurement of 151Sm at the CERN neutron time of flight facility (n_TOF)

The151Sm(n,gamma)152Sm cross section has been measured at the spallation neutron facility n_TOF at CERN in the energy range from 1 eV to 1 MeV. The new facility combines excellent resolution in neutron time-of-flight, low repetition rates, and an unsurpassed instantaneous luminosity, resulting in rather favorable signal/background ratios. The 151Sm cross section is of importance for characterizing neutron capture nucleosynthesis in asymptotic giant branch stars. At a thermal energy of kT=30 keV the Maxwellian averaged cross section of this unstable isotope (t(1/2)=93 yr) was determined to be 3100+/-160 mb, significantly larger than theoretical predictions.     

Absolute efficiency calibration of high-purity germanium detector in the range 120–8500 keV

This article reports the efficiency response curve of the high-purity germanium detector over the wide energy range, covering from 120 to 8500 keV. The efficiencies were measured for different counting geometries by using point radionuclide standards (mono-energetic as well as multi-gamma emitters) supplied by IAEA and the capture gamma-ray facility installed at PINSTECH nuclear reactor PARR-1. The measured efficiencies were required to fit with a suitable fitting function for interpolation within the energy range of interest. Several fitting functions were proposed in the literature covering different energy ranges. The functions giving the best fit to experimental data are presented. The work has successfully extended the response curve beyond 1500–8500 keV, which is the region where the standard calibration radionuclides are not available. The thermal neutron capture gamma-ray facility provided the collimated neutron beam, extracted from the core of the reactor and made to react with ammonium chloride target to produce the capture gamma rays for determining the efficiencies in the extended region. It was found that the capture gamma-ray provides a satisfactory solution to extend the absolute efficiency calibration in the MeV range. It was also found that the fitting function that is linear in its parameter was highly satisfactory up to 1500 keV but proved insufficient upto 8500 keV. The exponential function giving the good fit over the range has been presented. Good agreement has been found between the experimentally measured absolute efficiencies and the predicted result.     

New experimental measurement of natSe(n, γ) cross section between 1 eV to 1 keV at the CSNS Back-n facility

The ⁷⁴Se is one of 35 p-nuclei, and ⁸²Se is a r-process only nucleus, and their (n, γ) cross sections are vital input parameters for nuclear astrophysics reaction network calculations. The neutron capture cross section in the resonance range of isotopes and even natural selenium samples has not been measured. Prompt γ-rays originating from neutron-induced capture events were detected by four C₆D₆ liquid scintillator detectors at the Back-n facility of China Spallation Neutron Source (CSNS). The pulse height weighting technique (PHWT) was used to analyze the data in the 1 eV to 100 keV region. The deduced neutron capture cross section was compared with ENDF/B-VIII.0, JEFF-3.2, and JENDL-4.0, and some differences were found. Resonance parameters were extracted by the R-matrix code SAMMY in the 1 eV-1 keV region. All the cross sections of ^natSe and resonance parameters are given in the datasets. The datasets are openly available at http://www.doi.org/10.11922/sciencedb.j00113.00019.     

Fast Neutron Capture Cross Section of Natural Molybdenum

The radiative capture cross sections of natural Mo relative to the ¹⁹⁷Au (n,γ) were measured in the 0.7—1.4MeV neutron energy range,using a large liquid scintillator detector and the time-of-flight method.In the 0.01—2.0MeV neutron energy range,the theoretical calculation of (n,γ) reaction cross section for Mo was performed.The result of calculation is compared with the experimental data.     

Measurement of 232Th (n,γ) cross section at the CSNS Back-n facility in the unresolved resonance region from 4 keV to 100 keV

The neutron capture cross section of ²³²Th was measured at the neutron time-of-flight facility Back-n of China Spallation Neutron Source (CSNS) for the first time. The measurement was performed with 4 hydrogen-free deuterated benzene C₆D₆ liquid scintillation detectors, in the ES#2 experiment station on the beam line, at a distance of about 76 m from the neutron-production assembly. The total energy detection principle in combination with the pulse height weighting technique (PHWT) was applied to analyze the measured data. Results of the ²³²Th (n,γ) reaction cross section in the unresolved resonance region from 4 keV to 100 keV were obtained, which shows a good agreement with the existing experimental data from EXFOR, as well as with the evaluated data from the ENDF/B-VIII.0 and CENDL-3.1. In addition, the excitation function of ²³²Th (n,γ)²³³Th reaction in the unresolved resonance region was theoretically calculated by using the code TALYS-1.95. By fitting the experimental cross section and theoretical data, the average parameters in the unresolved resonance region were extracted. The datasets are openly available at http://dx.doi.org/10.11922/sciencedb.j00113.00015.     

MEASUREMENT OF THE FAST NEUTRON CAPTURE CROSS SECTIONS OF NATURAL NUCLEI Ta AND In

The neutron capture cross sections of Ta and In were measured in the energy range from 0.34 to 1.68MeV.A large liquid scintillator detector was used for detecting the prompt capture γ radiation.Two long-counters were used for monitoring the neutron flux.In order to reduce background the fast coincidence between the two half-spheres of the detector and the time-of-flight technique were used.The capture cross sections of Ta and In were determined relative to the standard cross section of Au.Present results were compared with others and discussed.     

Measurement of cross sections for inelastic cold-neutron scattering in metals and polymers by the method of (<Emphasis Type="Italic">n, γ</Emphasis>) analysis

The results obtained by measuring the cross sections for the inelastic scattering of very cold neutrons for a number of metals and polymers by the method of a neutron-irradiation analysis are presented. The method is based on simultaneously measuring events of inelastic scattering and neutron capture in the sample under investigation via recording gamma radiation with a semiconductor germanium detector. Neutron capture by a nucleus of the sample is accompanied by the prompt radiation of gamma rays having a known spectrum. Upon inelastic scattering, a neutron acquires thermal energy. Upon leaving the sample, this neutron is absorbed in a special converter that contains the isotope ¹⁰B. The capture of the neutron by a ¹⁰B nucleus is followed by the emission of a 477-keV gamma ray. The probabilities of capture and inelastic scattering are proportional to the respective neutron-interaction cross sections, and the ratio of the recorded detector counts corresponding to events of the two types does not depend on the spectrum of the incident flux of very cold neutrons or on the trajectory of neutron motion in the sample. The sought inelastic-scattering cross section at a fixed sample temperature is calculated by using this ratio and the known cross section for neutron capture by the sample isotope having a known gamma-radiation spectrum.     

Cross sections for 197Au(n, γ)198Au and 115In(n, γ)116mIn in the neutron energy region 2.0–7.7 MeV

The cross sections for the reactions ¹⁹⁷Au(n, γ)¹⁹⁸Au and ¹¹⁵In(n, γ)^116mIn have been measured with the activation method in the neutron energy region 2.0–7.7 MeV. The influence of background neutrons on the results was studied in considerable detail. The main problems are caused by low-energy neutrons produced by charged-particle reactions in the target material and secondary neutrons from nonelastic reactions in the sample and surrounding materials.The measured capture cross sections are generally lower than previous results and the deviation tends to increase with increasing neutron energy. The data are also compared with calculations based on the compound-nucleus model and quite good agreement is obtained.     

The decay of Se

The gamma-ray spectrum associated with the electron capture decay of ⁷⁵Se has been studied with Ge(Li) spectrometers. Coincidence spectra were taken with a Ge(Li)---Ge(Li) combination. The data do not support a recent report of several new gamma rays in the decay of ⁷⁵Se. Gamma-gamma angular correlation experiments were performed with a NaI(Tl)---Ge(Li) combination. The value obtained for δ(280 keV) is in excellent agreement with one recently reported value but in poor agreement with another. The ratio P_K/P_tot for the electron capture branch to the 401 keV level of ⁷⁵As has been determined, and the result agrees with previous experimental determinations.