热化数据处理功能研究与Thermc模块研发

热能区入射中子能量变化范围是110-5~5 eV,在这一范围内的中子能量与反应堆内材料靶核热运动的能量相当,中子与靶核的反应过程与其他能区截然不同。在该能区,需要考虑中子与堆内材料发生散射时,化学键、晶格结构以及分子热运动对反应过程的显著影响,对不同类型的材料,需要使用不同的理论方法和处理手段得到供输运程序使用的热化数据。基于热化数据处理的相关理论,研究了热中子散射数据的处理方法,同时在自主研发核数据处理软件RXSP中,开发了相应的核数据处理模块Thermc。在此基础上,使用Thermc模块基于ENDF/BVII.1核数据库加工得到热中子散射数据,经过与经典核数据处理软件NJOY的相应结果的微观比较以及若干宏观基准题检验,热化数据精度与准确性得到充分验证。     

蒙卡程序计算临界基准题测试检验ENDF/B-VIII.0核数据库

采用MCNP程序和ENDF/B-VII.1，ENDF/B-VIII.0核数据库，对119个模型构成的临界基准题进行了临界计算测试检验。此临界基准题模型包含233U、高浓铀、中浓铀、低浓铀和钚材料的临界实验系统，中子能量覆盖了快中子、中能中子和热中子能谱。采用ENDF/B-VIII.0核数据库的计算有效增殖因子k_eff结果与基准实验结果相对偏差的均值和标准差分别为?68.98×10?5和407.88×10?5，检验计算k_eff结果与基准实验结果的偏差与基准实验不确定度比值在1σ（σ为标准不确定度）以内、1σ～3σ区间和大于3σ的数量分别为107，9和3个；将此结果与相同条件下ENDF/B-VII.1核数据库的计算结果进行了比较，表明ENDF/B-VIII.0核数据库对临界计算更准确，与实验模型结果符合更好。     

蒙卡程序计算临界基准题测试检验ENDF/B-Ⅷ.0核数据库

采用MCNP程序和ENDF/B-Ⅶ.1,ENDF/B-Ⅷ.0核数据库,对119个模型构成的临界基准题进行了临界计算测试检验。此临界基准题模型包含²³³U、高浓铀、中浓铀、低浓铀和钚材料的临界实验系统,中子能量覆盖了快中子、中能中子和热中子能谱。采用ENDF/B-Ⅷ.0核数据库的计算有效增殖因子keff结果与基准实验结果相对偏差的均值和标准差分别为-68.98×10^-5和407.88×10^-5,检验计算keff结果与基准实验结果的偏差与基准实验不确定度比值在1σ（σ为标准不确定度）以内、1σ～3σ区间和大于3σ的数量分别为107,9和3个;将此结果与相同条件下ENDF/B-Ⅶ.1核数据库的计算结果进行了比较,表明ENDF/B-Ⅷ.0核数据库对临界计算更准确,与实验模型结果符合更好。     

氮化铀热中子截面的第一性原理计算

氮化铀（UN）因其较好的热物性和耐事故容错性成为先进动力堆的候选燃料,但目前热能区缺少可靠的UN热中子截面数据,这对于热中子反应堆物理计算是很不利的.本文基于量子力学的第一性原理,利用VASP/PHONON软件模拟计算了UN的声子态密度,以此为积分得到UN的定容比热容,并基于新制作的声子态密度,采用核截面处理程序NJOY/LEAPR,利用热中子散射理论,得到UN的S（α,β）数据,进而研究UN的热中子散射截面,并与传统压水堆的二氧化铀（UO₂）进行对比.结果表明：优化的晶格参数与数据库符合较好,UN声子态密度的声子项和光子项较UO₂的分隔更加明显,定容比热容计算结果与实验值一致,基于该声子态密度计算得到的UN中²³⁸U的非弹性散射和弹性散射截面比相同温度下UO₂中²³⁸U小,UN中N仅考虑了非相干散射部分,随着温度升高,UN弹性散射截面变小,非弹性散射变大,并在高能段趋于自由核散射截面.本文的研究结果填补了UN热中子截面数据的缺失,为下一步系统研究UN燃料在轻水堆中的中子学性能奠定了基础.     

(α,n)反应中子产额与能谱计算方法（英文）

发展了(α,n)反应中子产额与能谱蒙特卡罗直接模拟方法,该方法采用通用的连续碰撞方法与SRIM程序计算的阻止本领模拟α粒子慢化过程,采用基于JENDL/AN-2005加工后ACE格式数据库计算(α,n)反应中子产额与能谱。基于NPTS程序研制了(α,n)反应模拟功能,轻核(α,n)反应产额与实验结果符合较好,B、F、O靶出射中子能谱与实验结果符合较好,而C、Al、Si与实验结果有一定差异。     

(α,n)反应中子产额与能谱计算方法

发展了(α,n)反应中子产额与能谱蒙特卡罗直接模拟方法,该方法采用通用的连续碰撞方法与SRIM程序计算的阻止本领模拟 α粒子慢化过程,采用基于JENDL/AN-2005加工后ACE格式数据库计算(α,n)反应中子产额与能谱.基于NPTS程序研制了(α,n)反应模拟功能,轻核(α,n)反应产额与实验结果符合较好,B、F、...     

241Am-Be中子参考辐射的蒙特卡罗模拟研究

研究用于校准场所中子剂量监测仪表的241Am-Be中子参考辐射场计量特性。采用蒙特卡罗方法模拟了空气自由中子参考辐射(FRNR),GB/T 14055规定的最小尺寸中子参考辐射(SRNR)和实际中子参考辐射(ARNR)中不同检验点处中子周围剂量当量率、散射中子占比和能谱分布特征。研究结果表明,空气对FRNR中的剂量率和能谱分布影响小,近似为理想中子参考辐射;采用5%含硼聚乙烯作屏蔽的最小尺寸SRNR可减少热中子,降低散射中子占比,影锥法不适用于小尺寸中子参考辐射中对散射中子的修正;ARNR中的散射中子更少、占比更低,影锥法所得散射中子占比与理论值基本一致。     

ITER试验包层模块的中子学分析与设计

ITER试验包层模块(TBM)的中子学的设计和计算结果为TBM的其它大多数系统设计提供重要的数据依据。本文首先应用TRANSX程序完成基于FENDL2.0新库制作,以及中子输运程序和数据库的基准检验;然后应用二维中子输运程序TWODANT,计算和分析了中国氦冷Li₄SiO₄固体氚增殖剂的试验包层模块的功率密度分布、增殖区产氚特性、结构材料的中子辐照特性、结构材料和增殖材料的产氢和产氦等特性,并给出一个经合理优化的 TBM中子学初步设计结果。     

西安脉冲堆127I嬗变计算方法与实验验证

为了开展129I的热中子嬗变的研究,在西安脉冲堆上开展了127I靶件辐照实验。以探索实验条件,对127I靶件的嬗变率进行了蒙特卡罗计算,并与实验测量值进行了比对。利用NJOY程序,以ENDF/B VII.0库为基础,制作了127I在西安脉冲堆堆芯辐照温度下的MCNP格式截面库,与MCNP自带库(ENDF/B VI.2)同温度下截面库进行了比较,在不可分辨共振区做了改进,使用新制的截面库,利用MCNP程序对ORIGEN2数据库中的127I辐射俘获截面进行了修正,结合ORIGEN2程序分析了127I靶件在西安脉冲堆实际辐照后的嬗变率和核素的变化,研究了中子能谱和辐照时间对靶件嬗变计算的影响。使用MCNPX自带的燃耗模块CINDER90对127I靶件的嬗变情况进行模拟,结果与ORIGEN2基本一致,与实验数值有2%~3%的偏差,主要原因是MCNP计算中子通量密度存在误差。     

中子照相数值模拟与实验的对比

 介绍了热中子照相的MCNP数值模拟方法,模拟了300＃反应堆Maxwell谱热中子束穿透样品射到转换屏的过程,给出了热中子对铝、铅、铁、铜的穿透能力,分析了引起模拟与实验结果不同的原因。通过模拟得到了清晰的图像,对比数值模拟与在300#反应堆中子照相装置上的实验结果,数值模拟结果图像与实验结果图像非常相似;散射中子对图像的影响也符合相同的规律,随着样品与转换屏之间的距离的增大,散射中子对结果图像的影响越来越小,当样品与转换屏之间的距离为样品尺寸的2倍时可以忽略散射中子的影响。     

ENDF/B-VIII.β与ENDF/B-VII.1中水的热中子散射截面数据对比分析

以常见的慢化剂材料轻水为例,分析了ENDF/B评价库中两个版本ENDF/B-VⅢ.β与之前ENDF/BVⅡ.1中热中子散射截面数据的差异。由于ENDF/B-VⅢ.β与ENDF/B-VⅡ.1等两个版本中热中子散射截面的温度不尽相同,为定量分析同一温度下二者的差异,通过插值方法得到了任意温度下的热中子散射截面数据。对比发现,二者在同一温度下的热中子散射数据存在差异。相对于ENDF/B-VⅡ.1评价库版本而言,基于ENDF/B-VⅢ.β评价库版本加工得到的束缚在水中的氢的热中子散射截面与ENDF/B-VⅡ.1存在较为明显的差异,两个版本给出的低温情况下的中子与靶核碰撞后的平均散射角余弦在热区的低能段出现极小的负值。此外,当温度高于室温时,在热区的低能段ENDF/B-VⅢ.β给出的平均次级中子能量要稍大于ENDF/B-VⅡ.1给出平均次级中子能量。This work takes the traditional moderator material H₂O for example, the differences between ENDF/B-VⅢ.β and ENDF/B-VⅡ.1 versions from the ENDF/B nuclear evaluated library are analyzed. In order to compare the thermal neutron scattering data between ENDF/B-VⅢ.β and ENDF/B-VⅡ.1 versions under the same temperature, the interpolation method is used to obtain the thermal neutron scattering data under arbitrary temperatures. There are some differences between ENDF/B-VⅢ.β and ENDF/B-VⅡ.1 versions, the thermal neutron scattering cross sections of H bound in H₂O within ENDF/B-VⅢ.β is different with that of ENDF/B-VⅡ.1, the scattering angle cosines of the neutron and target nuclei from the two libraries are slightly smaller than zero in lower energy range within thermal range. Moreover, the second scattering energy spectrum from ENDF/B-VⅢ.β is slightly harder than that from the ENDF/B-VⅡ.1 in higher energy range within thermal range when the temperature is higher than room temperature.     

不同水温下的中子输运等效质量热运动模型

为了解决蒙特卡罗模拟S(, )模型只能求解特定温度条件下中子输运问题的局限性,建立了中子在不同温度液态水中输运的等效质量热运动模型。在分析自由气体热运动模型的基础上,采用不同的等效质量对中子与水中氢原子的弹性散射模拟过程进行改进,对中子穿过水层后的流量进行模拟计算,通过与S(, )模型的计算结果的比较,得到了5个不同的温度点水中氢原子的最佳等效质量。根据5个不同温度点的数据拟合给出了最佳等效质量和温度的函数关系。采用该模型计算得到的中子在不同温度条件下水中输运参数与S(, )模型相符。等效质量热运动模型突破了S(, )模型只能计算有限温度点的局限性,能有效处理300～800 K任意温度水中的中子输运问题。     

中子反应总截面测量系统关联不确定度的模拟

在15 MeV电子加速器驱动的白光中子源装置上进行了铍材料的中子总反应截面测量,测量结果与已有实验数据和ENDF/VII.1数据库的评价数据基本符合。为了得到由于加速器束流波动、飞行路径测量、靶厚度测量以及获取系统死时间等引起的测量系统的关联不确定度,利用Geant4模拟软件对整个实验装置、实验过程进行了模拟,经过对模拟中使用的中子反应总截面与模拟计算得到截面的比较分析,得到了实验系统关联不确定度的估计值。在模拟中采用了局部区域增加权重的方法来降低模拟运算时间。对模拟得到的中子飞行时间谱与实验测量得到的飞行时间谱进行了比较,并且对探测器处的中子产额也进行了比较,以此来验证模拟程序的可靠性。     

Measurement of neutron elastic scattering cross sections for carbon at 134 MeV

Angular differential neutron elastic scattering cross sections have been measured by using a ⁷Li(p,n) quasi-monoenergetic neutron beam. The neutron beam whose peak energy is 134 MeV was incident upon a natural carbon sample, and the scattering neutrons were measured by liquid organic scintillators with the time-of-flight (TOF) technique. The results were compared with the existing experimental data measured by a recoil-proton telescope, and the evaluated nuclear data of JENDL/HE-2007 and ENDF/B-VII.0.     

Simulation of Space Shuttle neutron measurements with FLUKA

FLUKA is an integrated particle transport code that has enhanced multigroup low-energy neutron transport capability similar to the well-known MORSE transport code. Gammas are produced in groups but many important individual lines are specifically included, and subsequently transported by the main FLUKA routines which use a modified version of EGS4 for electromagnetic (EM) transport. Recoil protons are also transported by the primary FLUKA transport simulation. The neutron cross-section libraries employed within FLUKA were supplied by Giancarlo Panini (ENEA, Italy) based upon the most recent data from JEF-1, JEF-2.2, ENDF/B-VI, JENDL-3, etc. More than 60 different materials are included in the FLUKA databases with temperature ranges including down to cryogenic temperatures. This code has been used extensively to model the neutron environments near high-energy physics experiment shielding. A simulation of the Space Shuttle based upon a spherical aluminum equivalent shielding distribution has been performed with reasonable results. There are good prospects for extending this calculation to a more realistic 3-D geometrical representation of the Shuttle including an accurate representation of its composition, which is an essential ingredient for the improvement of the predictions. A proposed project to develop a combined analysis and simulation package based upon FLUKA and the analysis infrastructure provided by the ROOT software is under active consideration. The code to be developed for this project will be of direct application to the problem of simulating the neutron environment in space, including the albedo effects.     

Inelasticity corrections for time-of-flight and fixed wavelength neutron diffraction experiments

Time-of-flight neutron diffraction methods are widely used to study the structure of liquids and glasses. The scattering nuclei in these experiments suffer nuclear recoil in the course of the neutron scattering process, which gives rise to distortions to both the self and distinct structure factors extracted from the data. These distortions are in general difficult to evaluate quantitatively, especially when the mass of the nucleus is similar to that of the neutron, such as when hydrogen is present in the material being studied. Traditional treatments of this effect generally assume the neutron energy is lower than the excitation energy of an atom, but for time-of-flight diffraction this is never the case, and the experiments typically sample a wide range of energy transfers from sub-meV to tens of eV. In addition, by attempting to produce an analytical correction, such methods invariably make a long list of approximations which can be difficult to justify in particular cases. Here, a model for the scattering kernal is developed based on the well known harmonic oscillator model [A.C. Zemach and R.J. Glauber, Phys. Rev. 101, 118 (1956)]. This is shown to have the correct first and second moments of the scattering kernal for both the self and distinct scattering, and is used to estimate the self and distinct scattering from a diatomic ‘dumbell’ molecule. The model gives a realistic account of the single atom scattering from light and heavy water over a wide range of incident neutron energies, but is not yet accurate enough to perform quantitative corrections. In lieu of a quantitative approach, a ‘top hat’ convolution method is developed to perform the subtraction of self scattering from real data, and to allow data from multiple detector banks to be merged into a single structure factor. The harmonic oscillator model is also used to address the question of inelasticity effects on the interference scattering. For the intramolecular correlations at least at low scattering angles up to ～40° it is found that the effect of inelasticity is rather small – around 0.6% on the estimated OH bond length for H₂O. Although the emphasis here is on time-of-flight diffraction, the model is quite general and can just as easily be applied to the case of fixed wavelength neutron diffraction where it also gives accurate results.     

定量中子数字成像散射校正的蒙特卡罗模拟

 中子数字成像过程中,散射中子可降低像质致使提取样品的定量信息变得困难。针对该情况,分析了中子微光成像系统图像散射降质的原理,采用点扩展函数的叠加来表征散射中子引起图像降质的过程,借助于蒙特卡罗方法（MC）对点扩展函数进行模拟和建模,将点扩展函数描述为样品厚度以及样品到探测器距离为参量的解析函数,研究了点扩展函数的计算方法。研究结果表明,借助于MC方法构建系统的点扩展函数之解析函数,并利用该函数对中子图像进行散射校正,是一种行之有效的定量中子数字成像散射校正方法。     

Mode-coupling crossover in viscous toluene revealed by neutron and light scattering

The dynamics of supercooled toluene, studied in a GHz-THz range by incoherent neutron and depolarized light scattering, is found to be in full accord with mode coupling predictions. Around the susceptibility minimum, neutron spectra are wavenumber independent and proportional to light scattering data; the fast -relaxation scaling law applies; amplitude and frequency diverge with power laws that extrapolate towards a crossover temperature K. Received: 20 June 1997 / Accepted: 3 November 1997