252Cf自发裂变n/γ TOF和TCC谱的MC模拟

时间关联符合法是主动法测量裂变材料特征信息的有效方法之一。首先使用MCNP程序模拟了单个BC-501A液体闪烁体探测器探测252Cf自发裂变n/γ飞行时间谱,模拟谱与实测谱符合很好;在此基础上,模拟了两个BC-501A探测器探测252Cf自发裂变n/γ时间关联符合谱。结果表明,n/γ时间关联符合谱包含了n-n、γ-γ、n-γ和γ-n符合成分。     

应用闪烁γ能谱测井系统对人工γ辐射核素的鉴别

在内华达试验基地(NTS)使用的标准γ能谱测井系统带有一个高效率、低能量分辨力的大体积碘化钠探测器。为了提高这个系统鉴别人工γ辐射核素的能力,发展和完善了一种简单方法,用于从低能γ谱中获取来自人工的部分。这一方法是使用一种参考数字模型得出的3个偏压光谱表示测井装置在大直径充满空气的钻孔中对天然钾、铀、钍系γ射线的谱响应。为了获取人工谱成分,这3个标准谱最早是使用常用     

~(67)Ga衰变的某些K壳内转换系数的测定

使用Si(Li)电子谱仪和Ge(Li)γ谱仪测定了~(67)Zn的5个跃迁的K内转换系数α_K。测量中使用归一化γ峰比电子峰的方法(NPG)。对以上二种探测器进行效率刻度,用BASIC语言编制γ谱和e谱的寻峰、求面积程序,在DIDAC-MULTI(8)系统上运算。     

基于相关性原理的嫦娥二号γ谱谱漂校正

为了解决嫦娥二号γ谱谱漂问题,提出了一种基于相关性原理的谱漂校正方法。以相关性原理为基础,介绍了嫦娥二号γ谱谱漂校正步骤,通过嫦娥二号γ谱Th元素和K元素特征峰峰位校正前后变化对比验证。实验结果显示,基于相关性原理的谱漂校正方法能够有效地缓解嫦娥二号γ谱谱漂影响,并且尽可能保持了谱线特征峰的原貌。     

MC法模拟不同中子源激励铀材料中子和γ飞行时间谱

为探索中子源激励探测铀材料应用技术,基于Geant4平台建立了中子源激励铀材料模拟中子和γ飞行时间谱的数学模型,模拟计算了利用不同中子源激励铀材料、使用不同探测器计数的中子和γ飞行时间谱,结果与已有相应实验谱特征相符。模拟结果表明:D-D和~(252)Cf源激励得到的中子和γ飞行时间谱有明显差异;在相同激励源和测量几何条件下,使用液体闪烁体探测器和塑料闪烁体探测器记录到的中子和γ飞行时间谱基本相同。本文结果可为外中子源激励探测铀材料技术研究提供参考。     

嫦娥二号γ谱的非线性谱漂校正

针对嫦娥二号γ谱的非线性谱漂特点,提出了一种基于能量对应的谱漂校正方法。选取了嫦娥二号γ谱线作为研究对象,进行谱漂校正实验。结果显示:该方法能够有效校正嫦娥二号γ谱的非线性漂移,使Fe峰和Mg/K峰的峰位漂移范围控制在±1道范围内。     

低强度脉冲中子束的数字式n/γ分辨测量

针对低强度脉冲中子束测量,使用高速数字示波器作为数据采集设备,配合BC501A液体闪烁体探测器组建了数字式脉冲形状甄别(Digital Pulse Shape Discrimination,DPSD)测量系统,实现了中子的n/γ分辨测量。系统工作时采集并存储探测器输出的中子与γ射线的脉冲波形及其记录时刻,利用DPSD方法甄别中子实现了中子脉冲高度谱统计;系统具有连续记录和具备时间戳的采集窗记录两种工作方式以适应不同的脉冲中子束强度,并通过分析数据记录中脉冲波形的位置或时间戳,实现了中子事件的时间信息统计。使用该系统在Am-Be中子源上使用采集窗工作模式开展了实验,成功获得中子脉冲幅度谱、中子时间谱以及n/γ甄别谱。     

低能γ射线谱测量岩性技术的初步研究

在分析野外地面γ射线谱的基础上,详细论述了低能γ射线谱及其与介质有效原子序数、岩性之间的关系。研究发现,不同地层、不同岩性的天然γ射线低能谱峰形态存在差异,主要表现在野外γ射线低能峰的峰位和低能峰前后两翼形状方面。据此,针对传统的野外γ射线能谱测量未能利用低能γ射线谱的问题,提出了一种利用低能γ射线谱段区分岩性的方法。     

质量控制谱法校正惰性气体氙β-γ符合谱能量漂移

针对CTBT放射性核素台站惰性气体氙β -γ符合谱能量漂移问题,提出了一种基于质量控制(QC)谱的谱能量漂移校正方法,利用质量控制谱中的γ能谱和二维β -γ符合谱分别对γ探测器和β探测器的能量漂移进行校正,确定氙样品二维β -γ符合谱中四种放射性氙同位素(131mXe,133mXe,133Xe和135Xe)的符合能量区域,实现了放射性氙同位素活度浓度的准确定量分析。     

人工神经网络解析CdZnTe探测器γ谱

半导体CdZnTe探测器具有体积小、分辨率高、可在室温下工作等优点而适用于野外便携式γ谱仪系统。由于CdZnTe晶体内电荷收集不完全导致γ谱产生低能尾巴,因而增加了常规谱解析的难度。采用了人工神经网络方法进行全γ谱法定性定量分析,可以充分利用γ谱所含信息,迅速准确地得出结果,避免了采用常规谱解析方法时低能尾巴对峰形拟合的影响。     

Evaluation of Shutdown Gamma-ray Dose Rates around the Duct Penetration by Three-Dimensional Monte Carlo Decay Gamma-ray Transport Calculation with Variance Reduction Method

For the evaluation of gamma-ray dose rates around the duct penetrations after shutdown of nuclear fusion reactor, the calculation method is proposed with an application of the Monte Carlo neutron and decay gamma-ray transport calculation. For the radioisotope production rates during operation, the Monte Carlo calculation is conducted by the modification of the nuclear data library replacing a prompt gamma-ray spectrum with a decay gamma-ray spectrum. By multiplying each correction factor, which is ratio of the actual activation level after shutdown to the production rate during operation, with each decay gamma-ray flux due to each radioisotope, the decay gamma-ray dose rate is evaluated. In order to improve the statistical error, a variance reduction method is proposed by the application of the weight window importance technique and the specification of the decay gamma-ray generation location. We identify the cell producing the decay gamma-ray which can contribute the decay gamma-ray flux in evaluation locations, and forcibly terminate the gamma-ray transport calculation in the cells except for the identified cells. In order to validate the effectiveness of the method, shielding calculation for actual ITER (International Thermonuclear Experimental Reactor) configuration is performed, and small statistical errors below criteria are obtained. The effectiveness of the proposed method for ITER design analysis is demonstrated.     

基于最小二乘法的航空?能谱解析

在天然辐射环境下,无法找到仅含单一天然放射性系列的近似无限大地层用于获取航空γ谱仪的响应谱,这是导致无法利用最小二乘法解析航空γ能谱的关键问题所在。本文基于介质互换原理、地层模块化与分能区多次模拟的思想,通过构建Monte Carlo组合模型,从而获得了含不同放射性物质的任意形状地层上空航空γ谱仪的响应谱。依据航空γ能谱测点上γ辐射来源与石家庄动态带分析,建立了一套可靠的最小二乘法航空γ能谱解析模型。通过对野外10 km测线分析发现,当地层含量大于4×10~(-6)时,该方法与标准方法分析结果相当。同时该方法为人工放射性核素响应谱的剥离提供参考。     

基于安全壳近程探测数据的事故源项反演方法

在发生核电厂严重事故时,为更加快速准确地估算释放至环境的气载放射性核素泄漏速率,提出了一种新的源项反演方法。该方法基于在安全壳附近主动布设的移动探测点所获取的γ能谱数据反演源项,研究了合适探测距离的选择、移动探测点的有效布设及准确反演单个核素泄漏速率的方法。根据研究结果,选择气载放射性核素中泄漏量及特征γ射线能量均相对高的⁸⁸Kr作为特征核素进行能谱分析;确定合适的探测距离范围为距离安全壳100 m以内;建立γ能谱数据与特征核素泄漏速率的关系,在数值上准确反演放射性核素的泄漏速率。     

航空伽玛能谱数据的校正与重组

介绍了航空伽玛能谱谱线校正的方法,并且对经过校正航空伽玛能谱数据进行数据窗口的重组.对航空能谱仪谱漂产生的原因和航空伽玛能谱数据的处理方法进行了介绍,根据我国自主研制的航空伽玛能谱仪谱线采集的特点和谱线合成方式,提出了采用变尺度校正的方式对谱线数据进行校正,并且根据航空伽玛能谱测量的要求,对窗口数据进行重组.实验结果表...     

Fission products and secondary gamma-ray spectra in a plutonium-fueled fast reactor

The fission products' gamma-ray and gamma-ray energy source spectra for a gas-cooled fast breeder reactor (GCFR) are calculated for different times after shutdown by modifying the RIBD computer code. The secondary gamma-ray energy source spectrum in the core of a GCFR, from fission, inelastic scattering, and capture reactions, is calculated using a typical GCFR neutron spectrum. The computer code LAPHANO is used to generate the multigroup (n, xγ) neutron-coupled gamma-ray transfer matrix. The weak dependence of capture and inelastic gamma ray source spectrum on the neutron flux spectrum has been noted. The fission products and secondary gamma-ray source spectra obtained can be used to calculate heat generation and refueling shielding requirements, etc.     

基于低能特征峰的自然伽玛能谱测井方法探讨及实践

提出了一种新的自然伽玛能谱测井的方法,该方法仅探测低能伽玛射线,选定~(214)Bi的609.3keV和~(208)Tl的583.2keV特征峰分别作为铀道和钍道的计数窗口.采用HPGe伽玛谱仪对测井模型进行实验测量,获得的铀道、钍道测井曲线效果很好,验证了该方法的可行性,表明基于HPGe探头的铀矿伽玛测井研究前景诱人.     

ACCURACY OF MEASUREMENT OF NATURAL GAMMA RAY SPECTRA BY HD－8004 NaI（T1）GAMMA SPECTROMETER

ＡＣＣＵＲＡＣＹ　ＯＦ　ＭＥＡＳＵＲＥＭＥＮＴ　ＯＦ　ＮＡＴＵＲＡＬ　ＧＡＭＭＡ　ＲＡＹ　ＳＰＥＣＴＲＡ　ＢＹ　ＨＤ－８００４　ＮａＩ（Ｔ１）ＧＡＭＭＡ　ＳＰＥＣＴＲＯＭＥＴＥＲＺｈｕＧｕｏｑｉｎ（朱国钦）ａｎｄＺｈｅｎｇＲｅｎｓｈｕ（郑仁淑）（Ｄｅ...     

KeV-Neutron Capture in Cesium-133, Gold-197 and Tantalum-181

The keV-neutron capture in ¹³³Cs, ¹⁹⁷Au and ¹⁸¹Ta was studied by measuring the cross section and the emitted gamma-ray spectrum. The neutron was produced with the KUR linear accelerator and a photoneutron target, and the samples were placed at 11.7 m from the neutron source. The gamma-rays following the keV-neutron capture were detected with a pair of C₆D₆ scintillators. The relative capture cross section between 3.2 and 270 keV was normalized to the absolute cross section at 24 keV obtained with an iron-filtered neutron beam. The results of ¹³³Cs and ¹⁹⁷Au are in good agreement with the recently measured and evaluated capture cross sections.

The capture gamma-ray spectrum was obtained by unfolding the observed spectrum with the response functions of the detector. The gamma-ray strength function, which represents the average gamma-ray transition probability, was derived with the spectrum fitting method. The level density distributions used in the calculation of spectrum fitting were investigated and it is found that the constant temperature level density is preferable. The gamma-ray strength functions for ¹⁹⁸Au and ¹³⁴Cs show the 5.5-MeV bump and the deficiency of strength compared with the tail of giant dipole resonance, and that for ¹⁸²Ta does not give the bump but shows the similarity to the tail of giant resonance. The results were compared with other data.     

能谱型核测井的逐点剥谱反褶积解释方法

本文以核测井中的γ能谱测井技术为背景,分析了目前采用的平均含量法和传统剥谱法等能谱型核测井定量解释方法的基本原理,指出了这些方法对不饱和混合矿层(即放射性元素分布不均匀的矿层)定量解释存在的缺陷.在引入强度型γ测井反褶积解释理论的基础上,改进能谱型γ测井定量方法,提出了一种分离放射性元素含量的新解释方法--能谱型核测井的逐点剥谱反褶积解释法.     

An enhanced differential evolution-based inverse radiation transport model for identification of unknown shielding layer thicknesses with gamma-ray spectrum

Identifying the geometric information of an object by analyzing the detected radiation fields is an important problem for national and global security.In the present work,an inverse radiation transport model,based on the enhanced differential evolution algorithm with global and local neighborhoods (IRT-DEGL),is developed to estimate the unknown layer thickness of the source/shield system with the gamma-ray spectrum.The framework is briefly introduced with the emphasis on handling the enhanced differential evolution algorithm.Using the simulated gamma-ray spectra,the numerical precision of the IRT-DEGL model is evaluated for one-dimensional source systems.Using the detected gamma-ray spectra,the inverse investigations for the unknown thicknesses of multiple shielding layers are performed.By comparing with the traditional gamma-ray absorption method,it is shown that the IRT-EDGL model can provide a much more accurate result and has great potential to be applied for the complicated systems.