在MCNP中考虑共振弹性散射的修正方法

蒙特卡罗方法采用自由气体模型来考虑中子与靶核的弹性碰撞中的热效应。传统的模型假设绝对零度下的弹性散射截面是常数,忽略了截面的共振效应所带来的影响。为在自由气体模型中考虑共振弹性散射效应,采用多普勒展宽舍弃修正方法,修正了连续能量蒙特卡罗程序MCNP的自由气体模型,并对Mosteller轻水堆多普勒基准题进行了分析。数值结果表明：对于轻水堆,在热态零功率的情况下,忽略共振弹性散射会高估燃料棒的无限介质增殖因数（k_∞）40～100 pcm,热态满功率下高估140～200 pcm;忽略共振弹性散射给燃料温度系数带来7%～15%正的偏差。同时分析了新的抽样方法对计算时间的影响,以及共振弹性散射效应对中子出射能量分布的影响。     

确定论方法中共振弹性散射的修正方法研究

截面加工软件(NJOY)程序求解无限均匀慢化方程时采用渐进散射核,忽略了共振弹性散射的影响,给特征值和多普勒系数的计算带来较大的误差。为在确定论程序中考虑这种效应,本文采用多普勒展宽舍弃修正(DBRC)方法修改了蒙特卡罗程序(MCNP)的自由气体模型,利用MCNP代替NJOY制作共振积分表。基于子群共振方法分析了轻水堆燃料棒的无限介质增殖因数和温度系数,并与MCNP的结果进行对比。数值结果表明,由于考虑了共振弹性散射效应,本文提出的修正方法提高了确定论方法的计算精度。     

氟盐冷却球床堆球栅元少群截面计算

氟盐冷却球床堆经10余年的发展,已逐步由预概念设计走向试验堆基准设计。本文采用确定论软件中的碰撞概率法模块对氟盐冷却球床堆球栅元建模,计算了其无穷增殖因数,少群均匀化总截面、俘获截面和裂变截面,并使用连续能量蒙特卡罗软件验证与分析。其中使用基于碰撞概率法的共振处理程序直接求解共振能区超精细群慢化方程,很好地处理了氟盐冷却球床堆的球型燃料元件所构成的双重非均匀系统。结果表明:确定论软件中碰撞概率法模块的计算结果与蒙特卡罗软件结果吻合,适用于对氟盐冷却球床堆进行少群截面加工。     

球床型氟盐冷却高温堆的初步中子学分析

为分析球床型氟盐冷却高温堆(PB-FHR)堆芯的关键中子学参数,建立了显式随机模型,基于随机填充方法计算了燃料球石墨基质内所有三层各向同性包覆颗粒(TRISO)颗粒的空间坐标,并采用离散元方法计算出堆芯活性区内全部燃料球的空间坐标。最后采用蒙特卡罗程序开展中子输运计算,分析燃料颗粒随机分布对堆芯中子学参数的影响。研究结果表明,TRISO颗粒的随机分布对栅元增殖系数、栅元群截面、活性区燃料球功率的影响较小,本文研究可为简化PB-FHR设计提供理论依据。     

超级均匀化方法用于球床氟盐冷却高温堆扩散计算

球床氟盐冷却高温堆的控制棒位于侧反应射层内,存在无裂变中子源且受堆芯泄漏谱强烈影响的强吸收体区域扩散计算难题。超级均匀化方法(Super Homogenization,SPH)被用于对氟盐球冷却床堆侧反射层中控制棒区域的强吸收体进行等效均匀化处理,同时堆芯除控制棒区域外采用谱修正方法(Spectra Modification,SM),将输运计算的结果作为基准进行验算。结果表明,SM-SPH模型能有效地计算球床氟盐冷却高温堆反射层控制棒价值及通量分布,并且较常规的SPH方法能更好地处理棒间干涉效应。     

氟盐冷却球床堆与HTR-10和MSRE的定量相似性分析

氟盐冷却球床堆是当前国际上一种新的研究堆型,尚无已经建造完成的反应堆,因此,选择相似且具有运行经验的反应堆作为基准题有助于堆芯核设计软件适用性分析。利用国际上常采用的相似性分析软件,可对熔盐实验堆(Molten Salt Reactor Experiment,MSRE)及10 MW高温气冷堆(10 MW high-temperature gas-cooled test reactor,HTR-10)与氟盐冷却球床堆的相似性进行分析,定量判断它们作为基准题的合理性。分析结果表明,MSRE和氟盐冷却球床堆的能谱峰位能量接近且堆内元素种类相近,二者相似程度较高;常温临界HTR-10和氟盐冷却球床堆冷却剂不同,且能谱峰位能量差异较大,二者相似程度较低。因此,MSRE是氟盐冷却球床堆中子物理设计软件较理想的基准题。     

球床氟盐冷却高温堆堆芯热工水力模拟

本文对球床氟盐冷却高温堆堆芯热工流体现象进行了研究。采用计算流体动力学(CFD)方法进行了三维建模和计算,得到了燃料元件球表面温度分布和堆芯冷却剂速度场、温度场和压力的分布,验证了稳态工况下氟盐对堆芯的冷却能力,分析了氟盐的特殊热工流体力学性质对堆芯安全的影响,结果可用于球床氟盐冷却高温堆的初步设计。     

球床结构对PB-FHR中子物理特性的影响研究

氟盐冷却高温球床堆（PB-FHR）中燃料球的装卸依靠浮力完成。球床结构受堆芯几何、装卸料速度、熔盐密度、熔盐流动等诸多因素的影响，其不确定性是反应堆物理设计和安全分析中重点考虑的内容。参考装卸料实验台架（PRED）的实验结果，采用蒙特卡罗程序（MCNP）完成了固态燃料钍基熔盐实验堆（TMSR-SF1）球床堆积密度、球床底部形状、冷却剂泄漏导致的液位下降等因素对中子物理关键参数的影响分析。结果表明，堆积密度的增加（50%~64%）导致燃料球装载量的增加、有效增殖因数的增加、温度系数的增加和控制棒价值的减小；相对于平坦型球床底部结构，外锥型结构会随着锥角的增加导致反应性先增加后减小，内锥型和斜面型结构则会引入负反应性；冷却剂泄漏事故引起的堆芯冷却剂液位大幅降低会导致堆积密实并引入负反应性。      

基于CITATION-ORIGEN2球床堆平衡态计算程序的实现

基于确定论中子扩散软件CITATION和点燃耗软件ORIGEN2,编写了球床堆分析程序COBBLE,以实现指定燃料球加载策略下的球床堆平衡态燃耗计算。COBBLE程序采用谱区能谱修正方法,通过迭代求解得到球床堆堆芯平衡态参数。本文选取简化的球床模块高温气冷堆(PBMR)堆芯进行建模,计算其功率分布及燃耗分布,并使用基于蒙特卡罗方法的球床堆燃耗计算程序PBRE进行了验证与分析。结果表明,COBBLE程序适用于球床堆的平衡态燃耗计算。     

1 GWt PB-FHR负荷跟踪运行特性分析

为研究熔盐堆系统在商业应用中的价值,分析其是否满足电网负荷的变化需求和安全运行的能力,本文以1 GWt球床式氟盐冷却高温堆（PB-FHR）为研究对象,仿真计算其在负荷跟踪模式下的瞬态行为和运行特性。以RELAP5/MOD4.0程序为研究工具,并植入相关的熔盐物性与计算关系式,建立氟盐冷却高温堆的热工水力系统与功率控制系统的仿真模型,对典型负荷工况参数变化情况下控制系统的响应特性进行仿真分析。结果表明：该氟盐冷却高温堆系统在设计的控制逻辑的调控下,展示出良好的负荷跟踪运行能力,堆芯功率能迅速响应负荷变化,功率超调和温度超调小,反应堆的运行参数始终处于合理的运行范围内。     

The impact of U resonance elastic scattering approximations on thermal reactor Doppler reactivity

The effects of accurate modeling of neutron scattering in ²³⁸U resonances are analyzed for typical light water reactor (LWR) and next generation nuclear plant (NGNP) lattices. An exact scattering kernel is formulated and implemented in a newly developed Monte Carlo code, MCSD (Monte Carlo slowing down), which solves a neutron slowing down in an infinite homogeneous medium and is used to generate resonance integral data used in the CASMO-5 lattice physics code. It is shown that the exact scattering kernel increases LWR Doppler coefficients by ∼10% relative to the traditional assumption of asymptotic elastic downscatter for ²³⁸U resonances. These resonance modeling improvements are shown to decrease hot full power eigenvalues by ∼200 pcm for LWRs and ∼450 pcm for NGNPs.     

Electron energy loss modelling in small volumes: A Monte Carlo study

In thin target and sub-volumes, electronic energy losses in single collisions vary considerably for individual charged particles. These fluctuations resulting from the stochastic nature of the interactions can be described through a simulation with Monte Carlo calculations. Models used in the present simulations to describe the electron scattering processes are derived from quantum mechanics. The resulting cross sections for energies up to 200 keV are shown for both processes, i.e. elastic and inelastic interactions. Influence of the Monte Carlo strategy adopted to calculate energy loss spectra (straggling functions) is discussed. Straggling functions calculated from the general purpose Monte Carlo code Penelope and the convolution method of Bichsel are included for comparisons. The results are new. In fact, disagreements have been found in the calculated energy spectra when using different strategies. These deviations are explained in the present study by investigating the thickness dependence on the electron energy. As a central result, energy deposition in silicon detectors can be described accurately when event by event Monte Carlo strategy is used.     

Bamboo-Lattice程序多群截面数据库的改进

本文基于ENDF/B-Ⅶ.0核评价数据库,利用核数据加工处理程序NJOY及LATTICE_PRE为Bamboo-Lattice程序研制了一套改进后的多群截面数据库NECL2.0。基于基准题和数值分析的结果表明：采用NECL2.0数据库计算得到的燃料组件的k_inf、裂变率分布、少群均匀化截面与参考解均吻合很好;考虑银铟镉共振对k_inf的计算精度可提高近1000 pcm,与参考解相比最大裂变率相对偏差从-0.97%降低到-0.53%;考虑包壳锆的共振对k_inf的计算精度可提高约60 pcm。     

NECP软件包中NECL子群数据与任意几何共振模块研制

本文基于子群方法对NECP软件包开发了多群数据库模块和子群共振计算模块。采用本实验室开发的二维任意几何输运程序矩阵MOC作为子群共振模块的求解器。使用MCNP与子群程序计算一系列的共振基准题,并比较了两者所计算的无限增殖因数k_inf和²³⁵U与²³⁸U的微观截面。结果表明,子群程序对任意几何有良好的适应性和精度,可适用于二维任意几何的共振计算。     

脉冲阵列中子测井探测器效率的研究

为了在石油脉冲阵列中子测井研究中充分地应用探测器的效率,运用蒙特卡罗（MC）方法通用程序MCNP对脉冲阵列中子测井仪的探测器的效率进行了计算研究,得到限满意的结果。计算结果可用于指导探测器的设计性能研究。     

Improvement of the resonance scattering treatment in MCNP in view of HTR calculations

The importance of an advanced neutron scattering treatment for heavy nuclei with strong energy dependent cross-sections such as the pronounced resonances of ²³⁸U has been discussed in various publications where the full double differential scattering kernel was derived. In this study the double differential kernel is confirmed by a purely stochastic approach. We evaluate the impact of this improved resonance kernel on High Temperature Reactors (HTR) using the Monte Carlo Code MCNPX. A comparison between the standard MCNPX scattering kernel and the new one is introduced. For the analyzed HTR-10 unit cells the new kernel leads to a decrease in criticality of 170–600 pcm depending on TRISO packing factor and fuel temperature and to an increase in magnitude of the Doppler reactivity coefficient by about 10%. The ²³⁹Pu inventory increases by up to 2.5% at the end of cycle.     

Range distribution of fluorine in F-implanted LiNbO3

Depth profiles of fluorine in ¹⁹F⁺implanted LiNbO³ have been accurately measured using the ₁₉F(p, γ)¹⁶O resonant nuclear reaction at E_R = 872.1 keV, with Γ = 4.2 keV. A proper convolution calculation method was used to extract the true distribution of fluorine from the experimental excitation yield curves. The experimental range distribution parameters, R_p and ΔR_p, were compared with those obtained by Monte Carlo simulation using a computer code developed recently in this group and with results obtained using the TRIM90 code. It shows that the experimental R_p values agree with the Monte Carlo simulation values very well, while the experimental ΔR_p values are larger than those obtained from the simulations. The simulation with our computer code improves the agreement between the experimental and calculated range straggling, ΔR_p.     

Neutron Self-Shielding Factor of Scattering-Predominant Resonance Foils

The neutron self-shielding factor of ⁵⁹Co resonance foil as an example of foils whose scattering cross section predominate over their absorption cross sections was obtained by both Monte Carlo method (analog) and the collision probability method for various thicknesses of the foil. Also, the transmission and reflection probabilities of neutrons which have various energies near the resonance energy were obtained, and the effects of multiple scattering of neutrons on the neutron self-shielding factor are discussed.

The neutron self-shielding factors obtained by the Monte Carlo method and by the collision probability method agreed well with each other in the cases Σ t ～ 4.0, in which the Monte Carlo method requires considerably longer machine time. Although for the cases of large Σ t (～4.0) the agreement is not always good because of the flat flux approximation in the collision probability method, the calculation time by Monte Carlo is conveniently short. A combination of both methods is useful in obtaining the neutron self-shielding factor of resonance foils.     

An ab initio Monte Carlo study of low energy positron and electron implantation in elemental metals and multilayers

A Monte Carlo code developed at Brookhaven to study positron and electron implantation in solids will be discussed. This code models the trajectories of a large number of positrons or electrons as they move through the material and uses this information to calculate stopping profiles, backscattered fractions and transmitted fractions. The particle-atom interactions are incorporated via elastic and inelastic scattering cross-sections. The incident particle energies vary from 1 to 10 keV and the simulation stops when the particle energy goes down to 25 eV or if the particle is backscattered. Main results of our Monte Carlo simulations of the mean implantation depth and implantation profiles for both semi-infinite metallic elements and multilayers will be discussed.