WIMS多群截面库更新时NJOY输入参数研究

以最新的微观评价库CENDL-2.1为基础,用先进的群常数制作程序系统——NJOY来制作新的WIMS69群截面库,研究不同的 NJOY输入参数对 WIMS程序所计算的积分量的影响,并给出了详细的参数研究结果,同时还分析和讨论了计算结果与基准实验结果的比对.WIMS multi group constant library is the associated working library of WIMS/D4 lattice code, and it was created by using rather old and obsolete data based on ENDF/B3 (1972). Recently, the new evaluated data files such as ENDF/B 6.5, JEF 2.2, CENDL 2.1 and JENDL 3.2 were released. It s necessary to update the old library by the new evaluated data. The parameter study is performed to investigate the sensitivity of the integral parameters calculated with WIMS/D4 on the selection...     

Measurement of differential cross sections of neutron-induced deuteron production reactions on carbon from 25 to 52 MeV

The angle-differential cross sections of neutron-induced deuteron production from carbon were measured at six neutron energies from 25 to 52 MeV relative to those of n-p elastic scattering at the China Spallation Neutron Source(CSNS) Back-n white neutron source.By employing the ΔE-E telescopes of the Light-charged Particle Detector Array(LPD A) system at 15.1° to 55.0° in the laboratory system,ratios of the angle-differential cross sections of the ~(12)C(n,xd) reactions to those of the n-p scattering were measured,and then,the angle-differential cross sections of the ~(12)C(n,xd) reactions were obtained using the angle-differential cross sections of the n-p elastic scattering from the JENDL-4.0/HE-2015 library as the standard.The obtained results are compared with data from previous measurements,all of which are based on mono-energic neutrons,the evaluated data from the JENDL-4.0/HE-2015 library and the ENDF-B/Ⅷ.0 library,and those from theoretical calculations based on INCA code and Talys-1.9 code.Being the first white-neutron-source-based systematic measurement of the angle-differential cross sections of neutron-induced deuteron production reactions on carbon in several tens of MeV,the present work can provide a reference to the data library considering the lack of experimental data.     

钍基熔盐堆用238群中子-48群光子耦合多群常数库的屏蔽基准验证

采用OKTAVIAN脉冲球实验对钍基熔盐堆用AMPX主库格式238群中子-48群光子耦合多群常数库进行了屏蔽基准验证,重点检验了该库中的F,Li,Be,C、Al,Si,Cr,Ni,Zr,Co,Cu,Mn,Mo,Nb,Ti,W,Pb同位素/元素的数据。采用SCALE 5.1程序系统中的XSDRN-PM程序进行一维屏蔽问题计算,将计算结果与实验测量数据及MCNP程序计算结果进行比较,发现中子泄漏谱的符合程度较好,而光子泄漏谱检验中发现大多数核素都出现了不同程度的高估。通过对GENDF格式到AMPX格式的转换程序MILER-4进行修正,解决了这一问题。通过对多群常数库的屏蔽基准验证,进一步证明了该库的可靠性。OKTAVIAN pulsed sphere experiment was used for Shielding Benchmarks of the AMPX formatted multi-group (238n-48γ) coupled neutron-gamma cross-section library for Thorium Molten Salt Reactor, of which the following isotopes/elements were checked-F, Li, Be, C, Al, Si, Cr, Ni, Zr, Co, Cu, Mn, Mo, Nb, Ti, W. One dimension shielding problem was calculated using XSDRN-PM program of SCALE 5.1 code system and results were compared with experiment results and MCNP calculated results, which shows that neutron leakage spectra agree well. Calculated results of photon leakage spectra of most facilities compared with MCNP results and experiment data are over-rated. MILER-4 code which is used for converting GENDF files produced by NJOY to the AMPX master library format is revised to solve this problem. The shielding benchmark verifications confirm the reliability of this new library.     

HENDL1.1/MG数据库和VisualBUS1．0程序的临界基准计算与分析

使用自主开发的一维输运／燃耗／可视化计算程序系统VisualBUS1．0和HENDL1．1／MG数据库,对^233U,^235U和^239Pu的热溶液临界球基准实验和^237Np,^241Am和^244Cm的金属快裂变临界球问题进行校核。和国际上广泛使用的各种程序和数据库的模拟计算结果以及相关实验结果进行综合对比和分析,初步验证了HENDL1．1／MG中裂变核素核数据的可靠性和应用性,同时也进一步证明了VisualBUS1.0程序的正确性。The evaluated critical safety benchmark experiments including some major elements of fission materials, such as ^233U, ^235U, ^239pu and ^237Np, ^241Am, ^244Cm, were simulated using the home-developed one-dimensionaltrasportation/burnup/optimization code system VisualBUS1.0 and HENDL1.1/MG, a multi-group working library of fusion-fission Hybrid Evaluated Nuclear Data Library, by FDS team. By the comparison with the measured resuits and the calculated values given in the International Handbook of Evaluated Criticality Safety Benchmark Experiments, HENDL1.1/MG data library and VisualBUS1.0 code are validated and qualified to be reliable.     

Evaluations on aero-optic effects of subsonic airborne electro-optical system

A simple method based on CFD code and Matlab for aero-optic effects is presented. Density fluctuation from CFD code due to the changes of such factors as altitude, speed, equipment location, and wavelength is introduced as an input to Matlab. The overall calculations are in Matlab. The results show that the performance of electro-optical (EO) system can be improved when the altitude increasing, the speed is as slowly as possible, and the equipment location moves to the leading edge of the airborne platform as far as possible, for the wavelength there is an optimum one when the indexes of contrast and resolution of the system are both considered. All of these methods can minimize the optical aberrations. Several numerical simulations demonstrate the method.     

Evaluations on aero-optic effects of subsonic airborne electro-optical system

A simple method based on CFD code and Matlab for aero-optic effects is presented. Density fluctuation from CFD code due to the changes of such factors as altitude, speed, equipment location, and wavelength is introduced as an input to Matlab. The overall calculations are in Matlab. The results show that the performance of electro-optical (EO) system can be improved when the altitude increasing, the speed is as slowly as possible, and the equipment location moves to the leading edge of the airborne platform as far as possible, for the wavelength there is an optimum one when the indexes of contrast and resolution of the system are both considered. All of these methods can minimize the optical aberrations. Several numerical simulations demonstrate the method.     

The CDF Run II Disk Inventory Manager

The Collider Detector at Fermilab(CDF) experiment records and analyses proton-antiprotion interactions at a center-of -mass energy of 2 TeV,Run II of the Fermilab Tevatron started in April of this year,The duration of the run is expected to be over two years.One of the main data handling strategies of CDF for RUn II is to hide all tape access from the user and to facilitate sharing of data and thus disk space,A disk inventory manager was designed and developed over the past years to keep track of the data on disk.to coordinate user access to the data,and to stage data back from tape to disk as needed.The CDF Run II disk inventory manager consists of a server process,a user and administrator command line interfaces.and a library with the routines of the client API.Data are managed in filesets which are groups of one or more files.The system keeps track of user acess to the filesets and attempts to keep frequently accessed data on disk.Data that are not on disk are automatically staged back from tape as needed.For CDF the main staging method is based on the mt-tools package as tapes are written according to the ANSI standard.     

A Model of BES Data Storage Management System

In this article we will introduce the system structure of a model built for BES data management and storage as well as the basic methods on how to establish the system.Additionally the analysis of the data structure,the data process,the selection of experimental program,the image manipulation and the key techniques will be discussed in detail,The model implements the setup of the system environment and all those functions from data loading,database cresting,data accessing,remote data process to data figuring.     

用于TRIGA堆计算的WIMS-D/4核数据库的评价

分别应用ＮＪＯＹ和ＧＡＳＫＥＴ程序将ＺｒＨ中Ｈ、１６６Ｅｒ和１６７Ｅｒ核素的６９群微观截面补充到ＷＩＭＳ程序的核数据库中，形成了用于ＴＲＩＧＡ堆计算的ＷＩＭＳ－ＣＮＤＣ库和ＷＩＭＳ－ＮＩＮＴ库．为了评价这两个核数据库是否正确，将它们与国际上通用的ＴＲＩＧＡ堆计算库ＷＩＭＳ－ＩＪＳ作了比较，验证了氢化锆中氢的声子特征；采用上述三种库分别计算了ＴＲＩＧＡ堆燃料栅元（标准－８．５燃料元件、标准１２燃料元件、ＬＥＵ燃料元件和ＦＬＩＰ燃料元件）的群常数、倍增因子随燃耗的变化以及燃料的负温度系数，并对结果进行了分析比较．结果表明，ＷＩＭＳ－ＣＮＤＣ库和ＷＩＭＳ－ＮＩＮＴ库适用于ＴＲＩＧＡ堆的计算． The 69 groups constants of Hin ZrH,166Er and 167Er generated by NJOY and GASKET codes are inserted into WIMS nuclear data library WIMS CNDC and WIMS NINT libraries used on RTIGA rector calculation are obtainedIn order to check WIMS CNDC and WIMS NINT libraries,the scattering cross section is compared with that in WIMS IJS li brary.The group constant,K->∞ and temperature coefficient are calculated by using WIMS C NDC,WIMS NINT and WIMS IJS.The results show the both libraries are...     

组件计算程序PANDA研发及初步验证

PANDA是上海核工程研究设计院研发的压水堆组件计算程序。该程序采用基于特征线方法（MOC）的一步化计算流程,即在不引入能群压缩和栅元均匀化的情况下直接进行组件层面的两维非均匀输运计算。多群数据库采用基于ENDF/B-VI制作的70群结构中子数据库,基于ENDF/B-VII的新版数据库也正在开发中。共振自屏计算采用了空间相关丹可夫方法（SDDM）,既具备燃料芯块分区计算的能力,又保留了传统Stammler方法的计算效率。多群非均匀输运计算采用二维模块化MOC方法,并辅以双重粗网有限差分(CMFD)加速技术,具有良好的计算精度和效率。对传统线性子链解析（TTA）方法以及多种矩阵指数方法进行了研究,选取了适合PANDA程序燃耗链的燃耗方程求解技术。基于以上基本模型开发了PANDA程序,并从程序模块、总体集成和核设计程序系统确认等三个层面,初步验证了PANDA程序的计算性能,表明了PANDA程序的工程设计计算能力。     

钍铀循环关键核素的多群数据库加工与初步验证

钍基先进核能系统的发展对核数据提出了新的需求。钍铀循环关键核素的多群数据库是堆芯物理设计与分析计算的基础。因此,基于权威核数据处理程序NJOY对ENDF/B-VII.1评价核数据库进行处理得到WIMS格式多群截面数据,利用专用更新处理程序WILLIE得到WIMS格式数据库,并利用多群堆芯计算程序WIMSD-5B对数据库进行了一系列临界基准检验,结果表明:基于ENDF/B-VII.1加工的WIMS库与WIMS库更新计划（WLUP）的网站上发布的最新版本WIMS库的计算结果基本一致,并且,在16个钍铀循环基准题检验中,新加工的WIMS库计算平均误差要比WIMSD5B程序的自带WIMS库的计算结果小0.225 3%,精度更高,可靠性更好。     

快堆中子学计算程序NECP-SARAX的改进与验证

NECP-SARAX是西安交通大学NECP团队开发的用于快中子反应堆的中子学程序系统。为准确处理快中子反应堆中中等质量核素散射共振以及非弹性散射导致的复杂的中子慢化效应,SARAX程序最初采用连续能量的蒙特卡罗方法计算中子能谱从而获得堆芯计算使用的有效多群截面。由于蒙特卡罗程序计算效率低,且在低能量段统计偏差较大,提出采用基于点截面的超细群方法计算中子慢化能谱,避免了蒙特卡罗方法产生参数时存在的缺陷。堆芯计算采用多群中子输运,通过优化简化几何建模,改进了程序的实用性。采用多种微扰方法计算堆芯各种反应性系数,提出了基于中子输运微扰理论的虚拟密度方法以计算堆内组件变形导致的反应性变化。在进行堆芯瞬态计算时,采用了点堆和改进准静态两种方法,可用于一般快堆和快谱ADS的典型事故分析。OECD发布的一系列快堆基准题测试表明,SARAX程序在快堆计算中具有良好的精度,达到了与国外著名快堆程序相当的水平。有效增殖因子与连续能量的蒙卡计算结果相比偏差在300 pcm以内。同时,由于引入了虚拟密度理论和三维时空动力学模型,程序功能更加完善,可以更好地满足快堆工程设计的需求。     

ScattPy: A new Python package for light scattering computations

We present a Python package developed for computing optical properties of non-spherical particles. It gives a user friendly flexible framework that takes advantage of programming with the modern language supported by the abundant library of scientific packages. The framework is designed to include the methods and interfaces to third-party codes required to treat scatterers of different shape and structure. We describe the current state of our package called ScattPy, briefly outline its range of applicability and note its outstanding accuracy for inhomogeneous particles with a multilayered structure.We also demonstrate some advantages of the ScattPy in particular when performing large-scale computations. Such languages as Python are known to simplify the data input and allow one to include new classes and objects (e.g. those required to define new scatterer shapes) without recompiling the code. The main benefits come from their ability to organize easily the output data as a database. In the ScattPy we use the SQLite database and illustrate how it is utilized in our investigation of the phase function dependence on the shape, size and structure of spheroids. By comparing the time consumption of the ScattPy to that of an equivalent code written completely in FORTRAN we show that there can be no essential performance losses when using Python.     

基于非线性迭代的压水堆瞬态计算程序开发

采用目前工业上成熟的非线性迭代计算策略,基于两群粗网有限差分方法和多群UNM节块方法,开发了针对压水堆工况的三维瞬态扩散计算程序。UNM方法采用解析基函数作为基函数,通过方程变换解决了解析节块法在临界节块计算不稳定的问题,提高了计算精度。热工计算采用单通道模型和燃料棒一维导热模型,相比目前堆芯在用的经验关系式方法,该模型可以更加准确地计算燃料棒温度分布。采用基于横向积分方程的三节块方法,可以有效减轻控制棒尖齿效应对瞬态计算的影响。为测试程序性能,采用NEACRP等基准算例对程序进行了校验。数值结果表明,开发的程序计算结果正确,适用于压水堆堆芯瞬态过程的模拟。     

混合评价核数据库HENDL1.0/MG/MC研制

根据世界几个主要核评价数据库,如ENDF/B 6(美国)、JEF 2.2(欧盟)、JENDL 3.2(日本)、BROND 2.2(俄罗斯)、CENDL 2.1(中国)和FENDL 2(IAEA/NDS),兼顾聚变、裂变以及聚变 裂变次临界混合堆设计研究的多种需要,经过甄别、筛选,最后集成为包含213个核素的基本评价文件,名为HENDL1.0/E的核评价数据库.在此基础上,利用目前流行的群常数加工程序系统NJOY和输运截面制备程序TRANSX制作两套用于中子或/和光子输运计算的输运截面工作库:①参考Vitamin J能群结构制作了175群中子和42群光子、中子 光子耦合多群工作数据库HENDL1.0/MG,可用于离散纵标Sn法程序计算;②连续能群结构、紧凑ENDF(ACE)格式中子截面库HENDL1.0/MC,可用于蒙特卡罗方法输运计算,如MCNP.另外还制作了可用于燃耗(嬗变)计算的燃耗库BURNUP.LIB和响应函数库RESPONSE.LIB两个专用数据库.同时,也对HENDL1.0综合评价核数据库的有效性进行了抽样测试、基准检验和初步确认. A Hybrid Evaluated Nuclear Data Library(HENDL) named as HENDL1.0 has been developed by Fusion Design Study (FDS) team of Institute of Plasma Physics, Academia Sinica (ASIPP) to take into account the requirements in design and research relevant to fusion, fission and fusion-fission sub-critical hybrid reactor. HENDL1.0 contains one basic evaluated sub-library naming HENDL1.0/E and two processed working sub-libraries naming HENDL1.0/MG and HENDL1.0/MC, respectively. Through carefully comparing...     

基于线性核素链的燃耗算法与蒙特卡罗程序耦合计算

根据线性核素链原理和反应堆燃耗的特点,建立相应核数据库并采用回溯算法生成自适应核素链,完成核素的遍历和计算,形成多群点燃耗计算程序,能够独立进行燃耗计算并具有完整的输出结果形式。同时将所开发的燃耗计算程序与蒙特卡罗程序进行耦合,完成接口模块的设计,形成可用于研究堆和核电站的燃耗-输运耦合计算工具。将所开发的输运-耦合计算程序应用于中国实验快堆首炉堆芯燃耗的计算,将计算结果与现有设计数据进行比较。经过初步分析表明:新的燃耗计算程序能够精确计算锕系核素含量,包括易裂变核素和生成量很小的次锕系核素。对某些锕系核素如Pu241的计算结果还存在较大偏差,这需要对计算结果进一步分析,来确认偏差是来自计算过程还是相关的截面数据。整个燃耗-输运耦合计算系统对裂变产物的处理和反应性变化的计算也与现有的设计数据符合良好。     

行波堆深燃耗的计算特点

行波堆属于新概念堆型,卸料燃耗深度可达400 GWd/tHM,是现有快堆的3~4倍、压水堆的6~8倍,较高的卸料燃耗深度对堆芯物理分析工具计算正确性提出挑战。基于此,以KYLIN-1程序为基础,从能谱、裂变产物核素重要性、燃耗计算误差累积等方面探究行波堆深燃耗计算特点。对典型行波堆六角形组件分析结果表明:低富集度铀组件寿期初、末能谱差别较大,采用单一权重谱制备的多群截面库用于其燃耗计算时,无限增殖系数偏差较大;为保证行波堆深燃耗计算的正确性,燃耗链应包含重要的70种裂变产物核素;行波堆深燃耗计算时,由于燃耗步增多累积的误差较小,无限增殖系数偏差每燃耗步约为0.001%。     

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。     

蒙特卡罗粒子输运程序JMCT研制

介绍了具有自主知识产权的蒙特卡罗(MC)粒子输运程序JMCT的初步研制成果。JMCT基于三维组合几何支撑软件框架JCOGIN,采用模块化,分成多层管理结构,可处理多群碰撞和连续能量碰撞,可进行粒子并行和区域分解并行两种并行方法,并具有良好的可扩展性和高速通信技术,同时配有可视化建模前处理软件。介绍了JMCT采用的多群物质碰撞机制,展示了程序模拟计算测试模型的结果,与MCNP程序计算结果一致。JMCT串行计算速度相比MCNP提高了约3 倍;在20 480个处理器核上模拟2109样本,并行效率可达70%。