简易Mie散射数值计算方法的研究

在回顾光散射理论发展史的基础上,分析了常规Mie散射计算实现过程中的问题,并论述一种改进的简易Mie散射数值计算方法。参照科学记数法定义了一种“EDecimal”类型的数据结构及其基本数学运算和三角函数运算。采用动态链表技术实现了高效的C++ Mie散射计算程序。该程序不仅可以用来处理极端条件下的Mie散射计算,而且显著降低了算法的时间复杂度,提高了执行效率。与相同精度要求下采用Wiscombe编写的MIEV0程序的计算结果进行了比较,并指出此程序精确可靠。     

Statistical verification of neutron-physics programs for calculations in support of nuclear safety

An algorithm for statistical verification of the XT26 code contained in the SAPHIRE-2006 code system is described. The results of conservative estimation of the calculation error in the K_eff calculations for different types of benchmark experiments are presented. The results of the statistical analysis of deviations from the experimental values are compared with the corresponding parameters obtained from the set of calculations performed using other codes.     

FLUKA Monte Carlo simulation code as used for radiation studies in the Alice experiment

The main features of the FLUKA Monte Carlo code, which can deal with transport and interaction of electromagnetic and hadronic particles, are summarized. The physical models embedded in FLUKA are described. Application of the code for the radiation background calculations. Especially, the origin and composition of the intense radiation field to be expected in parts of the ALICE detector for the coming multi-TeV LHC collider is described. It is important to evaluate the risk of radiation damage in detectors and electronics equipment. The text was submitted by the author in English.     

Parallelization of heterogeneous reactor calculations on a graphics processing unit

Parallelization is applied to the neutron calculations performed by the heterogeneous method on a graphics processing unit. The parallel algorithm of the modified TREC code is described. The efficiency of the parallel algorithm is evaluated.     

一维冲击波和爆轰波计算程序SSS

本文叙述一维程序SSS的理论和结构。介质采用流体弹塑性模型。爆轰反应有四种可选方式:Arrhenius律、C-J比容法、方波法和Forest Fire方程。爆轰产物可选用HOM或JWL状态方程。SSS程序的特殊功能有,激光效应、爆轰增长、强爆炸波、散心爆轰和瞬时爆轰等,初始起爆或能量释放位置可任意设定。本程序部分参考了美国洛斯阿拉莫斯实验室的一维程序SIN。本文列举的算例把这两个程序作了比较。     

Monte-Carlo algorithm for line-by-line calculations of thermal radiation in multiple scattering layered atmospheres

An algorithm for calculations of the longwave radiation in cloudy and aerosol slab atmospheres is described. It is based on the line-by-line and Monte-Carlo methods and is suitable for accurate treatment of both the gaseous absorption and the particulate multiple scattering in any spectral regions; other published algorithms as accurate as this can only make calculations in narrow spectral regions. It is recommended that this algorithm is well suited for radiation code validations as well as for theoretical investigations of radiative transfer in clouds and aerosols and satellite signal simulations.     

Space charge effects on stopped projectile fragment drift in gas

The results from a particle-in-cell code developed to describe the drifting of ions in an ionized buffer gas are described. The rate of ionization was found to have a dramatic effect on the collection efficiency of the heavy ions and results of the calculations agree well with recent observations.      

Simulation of the radiation fields from ionizing radiation sources inside the containment in an accident

In the present work, a set of codes used for simulations of the radiation fields from ionizing radiation sources inside the containment in an accident is described. A method of evaluating the gamma dose rate from a space and energy distributed source is given. The dose rate is calculated by means of the design point kernel method and using buildup factors. The code MCU-REA with the ORIMCU module is used for the burnup calculations.     

The OptModel high-precision optical-model program code

The OptModel high-precision optical-model program code aimed at solving a wide set of problems related to the elastic scattering and n, p, d, t, ^3,4,6He, ⁶Li nuclear reactions on spherical nuclei (or ones close to spherical) is described. A phenomenological optical potential in the Woods–Saxon form is used in this code. The main features of the program are described. The technique for solving a Schrödinger radial equation in the interior region is given in detail. The results from tests and research calculations are described. The results from executing a simultaneous analysis of a great deal of experimental data on elastic scattering at different energies to obtain the energy dependence of optical potential parameters are also presented.     

Analysis of features of hydrodynamics and heat transfer in the fuel assembly of prospective sodium reactor with a high rate of reproduction in the uranium-plutonium fuel cycle

The fast sodium reactor fuel assembly (FA) with U–Pu–Zr metallic fuel is described. In comparison with a “classical” fast reactor, this FA contains thin fuel rods and a wider fuel rod grid. Studies of the fluid dynamics and the heat transfer were carried out for such a new FA design. The verification of the ANSYS CFX code was provided for determination of the velocity, pressure, and temperature fields in the different channels. The calculations in the cells and in the FA were carried out using the model of shear stress transport (SST) selected at the stage of verification. The results of the hydrodynamics and heat transfer calculations have been analyzed.     

Effects of target fragmentation on evaluation of LET spectra from space radiations: implications for space radiation protection studies

We present calculations of linear energy transfer (LET) spectra in low earth orbit from galactic cosmic rays and trapped protons using the HZETRN/BRYNTRN computer code. The emphasis of our calculations is on the analysis of the effects of secondary nuclei produced through target fragmentation in the spacecraft shield or detectors. Recent improvements in the HZETRN/BRYNTRN radiation transport computer code are described. Calculations show that at large values of LET (> 100 keV/μm) the LET spectra seen in free space and low earth orbit (LEO) are dominated by target fragments and not the primary nuclei. Although the evaluation of microdosimetric spectra is not considered here, calculations of LET spectra support that the large lineal energy (y) events are dominated by the target fragments. Finally, we discuss the situation for interplanetary exposures to galactic cosmic rays and show that current radiation transport codes predict that in the region of high LET values the LET spectra at significant shield depths (> 10 g/cm² of Al) is greatly modified by target fragments. These results suggest that studies of track structure and biological response of space radiation should place emphasis on short tracks of medium charge fragments produced in the human body by high energy protons and neutrons.     

Helium trimer calculations with a public quantum three-body code

We present an illustration of using a quantumthree-body code being prepared for public release. The code is based on iterative solving of the three-dimensional Faddeev equations. The code is easy to use and allows users to perform highly-accurate calculations of quantum three-body systems. The previously known results for He₃ ground state are well reproduced by the code.     

400~1500 MeV质子轰击铅靶和钨靶的出射中子能谱的FLUKA和Geant4模拟研究

在ADS散裂靶系统的优化设计中,蒙特卡罗方法结合可靠的散裂反应理论模型进行中子学计算具有重要的作用。本工作利用Geant4程序中的INCLXX模型、BIC模型以及BERT模型和FLUKA程序分别模拟了597 MeV和1 500 MeV质子轰击薄铅靶不同出射角度的中子双微分截面,500,1 500 MeV质子轰击厚铅靶不同出射角度的中子双微分产额,以及400,600,800,1 000和1 200 MeV质子轰击厚钨靶在反角方向（175 °）的中子双微分产额,并与实验数据进行比较。研究表明,对于薄铅靶,Geant4程序的INCLXX模型和FLUKA程序模拟结果与实验符合得更好。能量在10～40 MeV范围内,BIC模型模拟结果明显高于实验数据,而BERT模型模拟结果略微低于实验数据。对于厚铅靶,在40 MeV左右所有的模拟结果都低于实验数据。对于厚钨靶,Geant4程序的BIC模型和FLUKA程序与实验数据符合得较好,INCLXX模型在能量高于60 MeV时模拟结果低于实验数据,BERT模型与实验数据差异较大。总体来看,Geant4程序的INCLXX模型和FLUKA程序进行ADS散裂靶相关的中子学的计算是合理和可靠的。The reliable Monte Carlo simulation codes coupled with nuclear reaction models play an important role in the neutronic calculation for the design and optimization of the ADS spallation target. In this work, the double differential cross sections at different angles produced from a thin lead target bombarded with 597 and 1 500 MeV protons, the neutron energy spectra at different angles produced from a thick lead target bombarded with 500 and 1 500 MeV protons, and the neutron energy spectra in the backward direction(175°) produced from a thick tungsten target bombarded with 400, 600, 800, 1 000 and 1 200 MeV protons are calculated with the Geant4 code coupled INCLXX, BIC and BERT models and the FLUKA code. The calculations are compared with the available experimental data. The results show that, for the thin lead target, the calculations with the Geant4 coupled INCLXX model and FLUKA code well reproduce the experimental results. In a energy range from 10 to 40 MeV, BIC model obviously overestimates the experimental results, and BERT model slightly underestimates the experimental results. For the thick lead target, all of the calculations underestimate the experimental results around 40MeV. For the thick tungsten target, the Geant4 coupled BIC model and FLUKA code well reproduce the experimental results. INCLXX model underestimates the experimental results above 60 MeV. BERT model bad reproduces the experimental results. Overall, the neutronic calculations with the Geant4 code coupled INCLXX model and FLUKA code for the ADS spallation target is reasonable and reliable.     

Zero-Dimensional Model to Study the Effectiveness of Plasma Heating and Thermal Energy Confinement in Globus-M Tokamak in Ohmic Heating Modes

Experimental study of thermal energy confinement in magnetic confinement devices is one of the fundamental problems in plasma physics. The data processing technique covering kinetic and magnetic measurements performed for the Globus-M tokamak is described. A zero-dimensional code has been developed on the basis of this approach making it possible to calculate important discharge parameters during the experiment (between discharges): the electron and ion stored thermal energy content, plasma effective charge, and confinement time. Good agreement of the zero-dimensional calculations and ASTRA modeling indicates that this approach can be applied for routine data processing in Globus-M in view of the specifics of the device.     

Testing of a Code for the Calculation of Spectra of Neutrons Produced in a Target of a Neutron Generator

The correctness of calculations performed with the SRIANG code for modeling the spectra of DT neutrons is estimated by comparing the obtained spectra to the results of calculations carried out with five different codes based on the Monte Carlo method.     

OCDMA的一种新型码的构造及实现

提出了一种新型OCDMA多维码构造方案。该多维码是在一维EPC(扩展的素数码)时域码的基础上,对其进行PC(素数码)跳频编码,并加上了偏振信息。然后通过偏振片和FBG(布拉格光线光栅)实现这种码的编解码,详述了其特点,最后描述了使用该地址码进行信息传输的OCDMA系统结构。计算表明该新型地址码具有更大的容量,能容纳更多的用户同时通信。     

Radiative properties of matter based on quantum statistical method

We present the preliminary results of our code OPAQS(opacity calculation using quantum statistical model) that is based on the self consistent Hartree-Fock-Slater model for the average atom. The code is capable of performing robust calculations of average charge state, frequency-dependent and mean opacities. The accuracy of the atomic model is verified by comparing the calculations of average charge state with various published results. The monochromatic opacities for iron computed at different sets of temperatures and densities are compared with LEDCOP. The Rosseland and Planck opacities for iron and aluminum are validated with some state-of-the-art codes. The results are in good agreement with the published data.     

94GHz渐变复合腔二次谐波回旋管的设计

根据注-波互作用自洽非线性理论,编写了分析渐变复合腔的计算程序,通过该程序,获得了工作模式对为TE021-TE031的注-波互作用腔体和相关电磁参量的优化结果。应用粒子模拟软件对设计的复合腔进行了模拟,模拟与数值计算结果基本一致。根据计算结果研制了二次谐波回旋管,在加速电压57.5kV、电流10A下,测得其工作频率为94GHz,输出模式为TE01,峰值功率和效率分别为156kW和27.1%。计算、模拟和实验结果基本一致。     

TREND code for reconstruction of neutron reaction cross sections and calculation of the Doppler broadening in the region of resolved resonances

The TREND code is developed for reconstruction of neutron cross sections in the region of resolved resonances from the data of the international evaluated nuclear data libraries using the Reich-Moore, Adler-Adler, and Breit-Wigner formalisms and for calculation of the Doppler broadening of the resulting cross sections within the classical approximation. The TREND code is incorporated into the MCU code package for Monte Carlo reactor calculations. The TREND and MCU codes have been used to evaluate the data of the ROSFOND data bank on uranium and plutonium isotopes in comparison with the data of the ICSBEP data bank.