基于网络的10MW高温气冷堆仿真系统

仿真系统基于计算机网络环境,可对10 MW高温气冷堆(HTR 10)的堆芯、主回路系统和蒸汽发生器等部件进行分析计算,模拟稳态和瞬态过程,并以图形界面动态显示仿真过程。同时可对仿真过程进行回放,对仿真数据结果进行分析并以二维、三维图形显示。该仿真系统不仅对高温气冷堆的工程设计、安全分析和人员培训有重要作用,且可对HTR 10主控室的操作人员进行现场支持及各项研究提供帮助。     

10MW高温气冷堆屏蔽计算分析

高温气冷堆是第4代核能系统的重要堆型之一,由于其堆芯体积庞大、几何结构复杂,屏蔽计算难度较大.本工作使用三维SN程序TORT对10 MW高温气冷堆进行屏蔽计算,并用ANISN、MCNP程序进行校核.结果表明,TORT程序计算结果与ANISN、MCNP程序计算结果符合很好.     

基于微机系统的高温气冷堆工程仿真机

基于微机系统的高温气冷堆工程仿真机（HTRSIMU）由清华大学核能技术设计研究院开发完成HTRSIMU运行于Windows98或Windows2000平台上,采用多进程、多显示器结构,具有人机界面友好、结构紧凑、操作方便、易于扩展等特点。它的模型包括10MW高温气冷堆（HTR－10）的一、二回路主要部件,能够对反应堆堆芯、主回路系统和蒸汽发生器等部件做详细的物理和热工分析计算,可以模拟正常运行和各种事故工况过程,仿真结果和蒸汽发生器等部件做详细的物理和热工分析计算,可以模拟正常运行和各种事故工况过程,仿真结果与HTR－10的设计值和安全分析报告符合得很好。利用HTRSIMU系统不仅可以进行高温气冷堆的工程设计、安全分析和人员培训,而且将来可以对HTR－10主控室的操作人员进行现场支持,给实际运行和各项研究提供帮助。     

高温气冷堆放射性总量计算程序研发与验证

堆芯放射性总量计算是核电站辐射防护设计、屏蔽计算和环境影响评价的基础。为进一步提高高温气冷堆堆芯放射性总量计算分析能力,自主研发了高温气冷堆堆芯源项计算程序NUIT,计算了HTR-10和HTR-PM堆芯内特定燃耗的燃料元件的放射性,并与KORIGEN程序的计算结果进行了对比。计算结果表明,NUIT程序可用于高温气冷堆堆芯放射性总量计算,并具有较好的计算精度和效率。     

10MW高温气冷实验堆的堆体结构特点

模块式高温气冷堆是当今世界上公认的先进反应堆堆型之一。固有安全性是它的最突出的优点。本文对10MW高温气冷堆的堆体布置进行了详细描述,并对10MW高温气冷堆的结构设计特点进行了分析。根据10MW高温气冷堆的特点,本文对该堆的固有安全性、制造工艺等方面的优点进行了论述。     

高温气冷堆氦气轮机系统电磁轴承冷却方案设计

电磁轴承是高温气冷堆立式氦气轮机系统的重要组件之一。本文针对高温气冷堆氦气循环发电中的高温电磁轴承,设计了4种综合冷却方案;采用前处理软件GAMBIT对电磁轴承腔体进行三维建模,使用流体力学计算软件FLUENT对模型进行了分析。模拟结果表明,通过合理的设计及优化,腔体可以得到有效冷却,并能将腔体温度控制在设备运行要求范围之内。     

HTR-ESS的堆芯物理仿真方法研究

为满足高温气冷堆工程模拟仿真系统（HTR-ESS）中实时的要求,研究开发了三维圆柱几何堆芯多群中子时空动力学改进准静态方法模拟计算程序,使中子动力学程序满足模拟过程的实时要求。模型利用拟合公式计算宏观截面,使截面可实时反映堆芯状态,与堆芯热工形成反馈。针对高温气冷堆中控制棒的特点,提出使用等效吸收体的方法对控制棒进行等效,等效方法避免了在计算中出现控制棒移动与网格不匹配的问题。最后给出动态过程的简单模拟结果,显示了建立的堆芯物理实时计算模型满足设计条件和要求。     

模块式高温气冷堆三维中子动力学计算分析

模块式高温气冷堆是国际上公认的安全性好、发电效率高、用途广的先进堆型。本文研究开发了三维圆柱几何堆芯多群中子动力学改进准静态方法模拟计算程序。对给定的模块式高温气冷堆堆芯物理模型进行了模拟计算。初始状态下,该程序计算结果与中子扩散程序CITATION吻合很好。动态情况下,模拟了堆芯反应性、堆芯相对功率以及堆内r,z网格上各群点中子注量率三维分布随时间的变化,计算结果与理论分析一致。     

HTR-10球形燃料元件模型分析

中国的高温气冷堆(HTR-10)属球床型高温气冷堆,采用球形燃料元件.在运行工况下,由于温度和辐照引起的应力变化会使燃料元件发生失效,对其进行分析可更多了解燃料元件内的情况.本文主要介绍了球形燃料元件的基本结构,以及燃料元件的温度分布、应力分析、破损率计算模型,并计算了在一定堆工条件下的温度和应力分布.     

高温气冷堆中子时空动力学实时仿真计算

本文研究开发了三维圆柱几何堆芯多群中子时空动力学改进准静态方法模拟计算程序。对给定的模块式高温气冷堆模型进行了模拟计算。在初始状态下,该程序的计算结果与中子扩散程序CITATION的计算结果吻合很好。在动态情况下,模拟了堆芯反应性、堆内各能群中子平均注量率和堆芯相对功率等物理量随时间的变化。计算结果与理论分析一致,在一定精度下,可达到实时仿真计算的要求。     

核设施退役虚拟仿真系统框架研究

退役核设施具有放射性,其退役过程危险且复杂,基于虚拟现实等技术的退役虚拟仿真系统可为退役工程提供辅助工具。本文在分析国内外研究成果的基础上,结合一专项退役工程的需求提出了该虚拟仿真系统的功能模块组成。基于软件开发技术进一步给出了系统的框架结构,并对各模块实现的相应技术进行了分析和探讨。分析中结合了计算机软硬件技术的最新研究成果,对退役中的切割、爆破、流体及放射性等的仿真技术进行了探讨。分析表明,基于普通个人计算机也可实现退役过程的全面虚拟仿真。经专家论证本方案具有可行性。     

A network-based system of simulation,control and online assistance for HTR-10

A network-based computer system has been developed for HTR-10. This system integrates three subsystems: the simulation subsystem (SIMUSUB), the visualized control designed subsystem (VCDSUB) and the online assistance subsystem (OASUB). The SIMUSUB consists of four functional elements: the simulation calculating server (SCS), the main control client (MCC), the data disposal client (DDC) and the results graphic display client (RGDC), all of which can communicate with each other via network. It is intended to analyze and calculate physical processes of the reactor core, the main loop system and the steam generator, etc., as well as to simulate the normal operational and transient accidents. The result data can be dynamically displayed through the RGDC. The VCDSUB provides a platform for control system modeling where the control flow systems can be automatically generated and graphically simulated. Based on the data from the field bus, the OASUB provides some of the reactor core parameters, which are difficult to measure. This integrated system can be used as an educational tool to understand the design and operational characteristics of the HTR-10, and can also provide online support for operators in the main control room, or as a convenient powerful tool for the control system design.     

核动力仿真技术及其发展

文章评述核动力仿真技术的发展状况及其特点，重点分析了核动力仿真机的发展，探索了核动力仿真技术发展的新动向。分析指出：模块化、集成化、数字化、可视化、虚拟化、网络化和智能化仿真是未来核动力仿真技术发展的重要趋势；核动力仿真逐渐突破传统的模式，向以三维数字化仿真设计为基础的核动力系统设计、制造方面拓展；以全寿期管理为目标的数字化核电厂设计是未来核动力仿真技术的一个重要的研究与应用领域。     

Radiation dose rate map interpolation in nuclear plants using neural networks and virtual reality techniques

This paper reports the most recent development results of a simulation tool for assessment of radiation dose exposition by nuclear plant’s personnel, using artificial intelligence and virtual reality technologies. The main purpose of this tool is to support training of nuclear plants’ personnel, to optimize working tasks for minimisation of received dose. A finer grid of measurement points was considered within the nuclear plant’s room, for different power operating conditions. Further, an intelligent system was developed, based on neural networks, to interpolate dose rate values among measured points. The intelligent dose prediction system is thus able to improve the simulation of dose received by personnel. This work describes the improvements implemented in this simulation tool.     

Deployment analysis and remote accessibility verification for a maintenance task in a PRIDE digital mock-up

This study introduces an advanced modeling and simulation system that can verify and optimize a maintenance procedure at the early design stage of a virtual engineering system. System architecture, which is composed of modules used to analyze deployment of devices that deal with radioactive materials in a digital mock-up, and modules used to simulate accessibility of a remote manipulator for maintenance tasks, are discussed. Based on this architecture, new technology that enables a maintenance analyst to analyze pyroprocessing is proposed. Workspace analysis for remote manipulators, which can optimize a maintenance task at the radiation control area, is introduced. The mathematical background, with respect to the forward and inverse kinematics for a virtual manipulator accessing devices in a virtual environment, is described to establish a remote accessibility. Virtual prototyping is illustrated to carry out an experiment on the deployment analysis of devices and remote accessibility by a haptic device.     

某型虚拟冲击器的设计及数值模拟

虚拟冲击器能够吸入空气中的气溶胶并收集特定粒径的颗粒。一般来说,常用的虚拟冲击器的切割粒径较大,工作流量也较大,对于某些限制流量的工况可能不适用。在本研究中,开发了一种新型多缝虚拟冲击器,且喷嘴附近注入清洁空气,能够减小气溶胶在冲击器内的损失。通过数值模拟的方法分析该虚拟冲击器的性能,结果表明,即使总流量为36 L/min,也能获得0.08 atm的低压降,利用具有清洁空气的狭缝喷嘴虚拟冲击器,可将切割粒径降到0.2~0.4 μm,并以1.8 L/min的流量收集起来。     

Analysis and validation center for ITER RH maintenance scenarios in a virtual environment

A facility for detailed simulation of maintenance processes in the ITER Hot Cell Facility (HCF) has been taken into operation. The facility mimics the Remote Handling (RH) work-cells as are presently foreseen. Novel virtual reality (VR) technology, extended with a physics engine is used to create a realistic setting in which a team of Remote Handling (RH) operators can interact with a virtual Hot Cell environment. The physics engine is used to emulate the Hot Cell behavior and to provide tactile feed-back of the (virtual) slave. Multi-operator maintenance scenarios can be developed and tested in virtual reality. Complex interactions between the RH operators and the HCF control system software will be tested. Task performance will be quantified and operational resource consumption will be estimated.     

Real-time virtual EAST physical experiment system

As a large fusion reaction device, experimental advanced superconducting tokamak (EAST)’s internal structure is complicated and not easily accessible. Moreover, various diagnostic systems and complicated configuration bring about the inconveniency to the scientists who are unfamiliar with the system but interested in the data. We propose a virtual system to display the 3D model of EAST facility and enable people to view its inner structure and get access to the information of its components in various view sights. We would also provide most of the diagnostic configuration details together with their signal names and physical properties. Compared to the previous ways of viewing information by reference to collected drawings and videos, virtual EAST system is more interactive and immersive. We constructed the browser-oriented virtual EAST physical experiment system, integrated real-time experiment data acquisition, plasma shape visualization and experiment result simulation in order to reproduce physical experiments in a web browser. This system used B/S (Browser/Server) structure in combination with the technology of virtual reality – VRML (Virtual Reality Modeling Language) and Java 3D. In order to avoid the bandwidth limit across internet, we balanced the rendering speed and the precision of the virtual model components. Any registered user can view the experimental information visually and efficiently by logining the system through a web browser. The establishment of the system provides the framework basis for a comprehensive virtual EAST cooperative physical experimental environment.     

Nuclear plant’s virtual simulation for on-line radioactive environment monitoring and dose assessment for personnel

This paper reports the use of nuclear plant’s simulation for online dose rate monitoring and dose assessment for personnel, using virtual reality technology. The platform used for virtual simulation was adapted from a low cost game engine, taking advantage of all its image rendering capabilities, as well as the physics for movement and collision, and networking capabilities for multi-user interactive navigation. A real nuclear plant was virtually modeled and simulated, so that a number of users can navigate simultaneously in this virtual environment in first or third person view, each one receiving visual information about both the radiation dose rate in each actual position, and the radiation dose received. Currently, this research and development activity has been extended to consider also on-line measurements collected from radiation monitors installed in the real plant that feed the simulation platform with dose rate data, through a TCP/IP network. Results are shown and commented, and other improvements are discussed, as the execution of a more detailed dose rate mapping campaign.     

Dynamic minimum dose path-searching method for virtual nuclear facilities

Walking path-planning technology can be taken as a radiation protection measure to reduce radiation exposure to workers in radiation environment, and to guarantee work order and efficiency. Considering the nuclear facilities scene can be dynamic and changeable, we designed a dynamic minimum dose walking path-searching method based on the static minimum dose walking path-planning method earlier, and built path-planning simulation platform for nuclear radiation environment with virtual reality technology to plan walking path and virtual simulation.