高温气冷堆氦气轮机基本特性研究

高温气冷堆氦气轮机循环被认为是将来核能发电领域中最有潜力的方案之一。首先对高温堆氦气轮机循环进行分析和优化 ,然后着重从热力学和气体动力学角度研究氦气轮机的基本特性。结果表明 ,氦气轮机有两个主要设计特点不同于通常的燃气轮机 :一个是叶片级数多 ;另一个是叶片高度低 ,这些特性分别由氦气的物性和闭式循环的高压所导致。     

高温气冷堆技术背景和发展潜力的初步研究

从能源供应和环境保护的角度 ,论证了核能工业的重要性 ;然后对高温堆氦气轮机循环进行了分析 ,结果表明发电效率达 4 7 9% ;最后通过几种先进堆型的对比 ,阐明了高温气冷堆的技术优势。高温气冷堆很有潜力成为第四代核能系统的堆型之一。     

氦气轮机瞬态运行特性仿真研究

通过建立高温气冷堆氦气轮机各部件的集总参数数学模型,利用Matlab/Simulink(仿真软件构建仿真模型,对氦气轮机起动过程的瞬态运行特性进行了仿真研究,给出了高、低压压气机运行线以及压气机出口压力、堆芯进出口温度、涡轮功率、压气机功率、发电机功率等主要参数随堆芯功率的变化曲线.模拟计算结果表明,在氦气轮机起动过程...     

高温和超高温气冷堆动力转换方案研究

动力转换单元是高温和超高温气冷堆的重要组成部分。本文对高温和超高温气冷堆的动力转换单元进行研究。从4个关键参数（反应堆出口温度、反应堆入口温度、压缩比和主蒸汽参数）入手,对5个循环方案进行比较分析。综合考虑各种工程因素,上位循环为简单氦气透平循环、下位循环为有再热的蒸汽轮机循环的联合循环方案是具有竞争力的,其中下位循环在高温气冷堆范围是亚临界参数循环,在超高温气冷堆范围是超临界参数循环。联合循环可实现高温和超高温气冷堆热量的高效率转化,且反应堆入口温度在反应堆压力壳材料允许的范围内,具有足够的安全性。     

高温和超高温气冷堆动力转换方案研究

动力转换单元是高温和超高温气冷堆的重要组成部分。本文对高温和超高温气冷堆的动力转换单元进行研究。从4个关键参数(反应堆出口温度、反应堆入口温度、压缩比和主蒸汽参数)入手,对5个循环方案进行比较分析。综合考虑各种工程因素,上位循环为简单氦气透平循环、下位循环为有再热的蒸汽轮机循环的联合循环方案是具有竞争力的,其中下位循环在高温气冷堆范围是亚临界参数循环,在超高温气冷堆范围是超临界参数循环。联合循环可实现高温和超高温气冷堆热量的高效率转化,且反应堆入口温度在反应堆压力壳材料允许的范围内,具有足够的安全性。     

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。     

高温气冷堆回热循环及透平机组的初步研究

结合了模块式高温气冷堆与气体透平循环技术的高温堆气体透平循环是核电领域中的全新概念，为提高核电的安全性和经济性提供了新的思路，具有很强的竞争优势。其中，高温气冷堆回热循环是该方案的主流。在高温堆回热循环方案中，氦气透平机组的工作介质为氦气，其物性与空气有很大的不同，因此，氦气透平与燃气透平在热力参数、气动参数、尺寸、级数等方面有着较大的差别。本研究对回热循环以及氦气透平进行了初步分析，并通过与燃气透平的比较，揭示了回热循环与氦气透平的一些基本设计特点。     

多用途高温气冷堆

美国核学会访华代表团成员理查德(C.L.Richard)于1980年9月29日在北京作了题为《多用途高温气冷堆》的报告,摘要如下:高温气冷堆 HTGR 是唯一的一种能同时发电和提供工业用热的多用途核反应堆。一座85万千瓦(热)的高温气冷堆热源代替化石燃料,一天可以节省石油11,500桶或3,000吨煤(热当量)。美国研究的发电用高温气冷堆,有蒸汽循环高温气冷堆(HTGR-SC)[功率从84—336万千瓦(热)]和氦气轮机高温气冷堆(H-TGR-GT)(功率为200万千瓦(热)]两种。美国研究的发电和供热两用高温气冷堆有三种:第一种是利用圣符仑堡堆已有技术     

高温气冷堆简化型联合循环特性研究

高温气冷堆具有900~1000℃的出口温度而使其具备采用联合循环发电的潜力。在典型高温气冷堆氦气 蒸汽联合循环中,氦气回路多采用预冷器等设备以降低压气机入口温度和压缩功,但这也使反应堆的入口温度过低而影响联合循环效率的进一步提高。为提高循环效率,对联合循环中的预冷器对循环效率的影响进行了热力学分析,提出了联合循环中是否需设置预冷器的判据,并根据这一判据提出了一种简化型联合循环,即无预冷器的联合循环。简化型联合循环的优化结果表明,在950 ℃的反应堆出口温度下,其循环效率可达52.2%,较典型联合循环的效率提高了1.4%,较回热循环的效率提高了1.7%。与回热循环相比,在反应堆出口温度较高而其入口温度要求较低的工况下,简化型联合循环更具有优势。     

中间换热器的传热和阻力特性

中间换热器在高温气冷堆氦气透平间接循环发电系统中是耦合高温气冷堆和氦气透平的关键部件,承担着将高温气冷堆中高温氦气的能量传递到氦气透平回路的任务.中间换热器给氦气透平的设计和运行维护带来方便,但它的传热与阻力性能不可避免地影响循环效率,因此,中间换热器的设计和选型需综合考虑传热效率、压力损失、材料性能和紧凑度等因素.本文介绍了印制板式换热器(PCHE)的主要特点,分析了它在间接循环系统中应用的可行性,重点研究了该中间换热器的传热和流动阻力特性,以及影响PCHE换热效率和压力损失的主要因素.在此基础上,提出了优化中间换热器传热和阻力特性的途径和方法.     

研究堆运行许可证有效期延续申请审查策略

生态环境部第8号令《核动力厂、研究堆和核燃料循环设施安全许可程序规定》对核动力厂、研究堆和核燃料循环设施运行许可证件延续事项作出了新的规定。为推动我国研究堆老化管理标准体系建立,分析了我国研究堆延寿审查策略发展历程,结合高通量工程试验堆等研究堆运行许可证有效期延续申请审查工作中的几个关键问题,提出了以定期安全审查为主、重点依据老化管理并兼顾技术规格书审查及差异性审查的审查策略,研究成果为我国研究堆老化管理法规标准的建立提供了实践经验及理论指导依据。      

日本JNC瑞浪地下实验室项目研究活动介绍

本文介绍了日本核燃料循环开发研究所（JNC）瑞浪地下实验室（MIU）的研究目标、内容和工作计划，对高放处置的背景作了简要说明。     

BWR pipe crack control using hydrogen water chemistry: Status report on Dresden-2 program

One of the proposed remedies for intergranular stress corrosion cracking of stainless steel piping in BWRs is an alternative water chemistry called hydrogen water chemistry (H₂WC) that involves suppression of reactor water dissolved oxygen to ≤ 20 ppb via hydrogen injection to the feedwater in conjunction with control of conductivity to ≤ 0.3 μ mho/cm. A long-term verification program, over two or three 18 month fuel cycles, was started at Commonwealth Edison's Dresden-2 reactor in April 1983 (Cycle 9). This paper describes the results of the water chemistry changes, structural material and fuel evaluations, and plant radiation level changes during Cycle 9, which ended in October 1984.To date the results of the verification program are very encouraging. They indicate that the alternative water chemistry, based on hydrogen additions to the feedwater to suppress oxygen and low conductivity, can be maintained in a large operating BWR, and that it does mitigate IGSCC in stainless steel recirculation piping. Monitoring of fuel and plant materials will continue in Dresden-2 at least through Cycle 10 to confirm the absence of any unusual side effects of this remedy for IGSCC.     

Multilateral Assessment of the Fast Reactor System as a Component of the Future Sustainable Nuclear Energy and Paths for the System Deployment

The paper reviews main findings of the Joint Assessment Study on a Nuclear Energy System (NES) based on a Closed Nuclear Fuel Cycle with Fast Reactors (CNFC-FRs) that was performed within the IAEA project INPRO.     

核设施的设备老化控制研究策略

指出了核设施中普遍存在着设备老化问题,及设备老化控制研究的必要性.探讨了分层次开展设备老化控制研究的策略及各层次的研究思路,还对运用"生命周期评价”方法开展设备老化控制研究的可行性作了探讨.     

Optimization of refueling cycle length by an enhanced PSO with novel mutation operator

In this paper, a new method for optimizing the fuel arrangement in a WWER-1000 reactor core during refueling cycle is presented. Finding the best configuration corresponding to the desired pattern, an enhanced PSO with a Novel Mutation operator is applied. WIMS and PARCS (Purdue Advanced Reactor Core Simulator) codes are used to calculate the neutronics cross sections and multiplication factor of core with corresponded power peaking factors (PPFs) during burn up cycles, respectively. Cross sections and burn up during cycle length were calculated by WIMS code, then core parameters were calculated by PARCS and finally hybridization of intelligent PSO (Particle Swarm Optimization) method and novel mutation were used to obtain optimal arrangement. The purposed algorithm is based on increasing burn up value and refueling cycle length and by keeping power peaking factor in safe margins. In this way, neutronic parameters of the reactor during operation cycle from BOC (Begin Of Cycle) to EOC (End Of Cycle), were calculated. Implementation of this algorithm has been done in MATLAB. In this case, Bushehr WWER-1000 NPP reactor was studied. The comparison between results and Final Safety Analysis Report (FSAR) data shows good agreement.     

Progress on the Plant Design Concept of Sodium-Cooled Fast Reactor

An innovative concept of sodium-cooled fast reactor, named JAEA Sodium Cooled FR (JSFR) has been created and modified through the Feasibility Study on Commercialized FR Cycle System, aiming at full satisfaction of the development targets. A modified concept of JSFR applied double-wall straight tube type steam generator (SG) which is excelling in safety for sodium-water reaction has been developed. In addition, decay heat removal system suitable for the straight tube SG has been selected and in-service inspection and repair capabilities have been improved. As the result of this study, the potential to realize this plant concept has been obtained through evaluation concerning safety and economics.     

Burnup management simulator for small and medium sized reactors

We propose a novel burn up management simulator scheme which would maximize the discharge burn up of Small and Medium Sized Reactors (SMR) by optimum choice of Fuel Cycle Length (FCL). In this simulator, the objective being to maximize the burn up of all the subassemblies of the reactor so that burn up loss in them is a minimum and the plant availability factor is maximized. The simulator can be used both for the conventional batch refueling as well as the once through cycle schemes. Further, the designer has the option to choose a particular FCL depending upon the percentage loss in burn up.     

中国煤电链温室气体排放系数及其与核电链的比较

利用全寿命循环分析方法对煤电链的温室气体排放进行了较全面的综合分析,给出了我国煤电链中各个环节及其总的温室气体排放系数,并与核电链的温室气体排放进行了比较。煤电链总的排放系数为１３０２．３ ｇＣＯ２／ｋＷｈ,是核电链的几十倍。与煤电链相比,核电至少不会加剧温室气体的进一步排放。发展核电是能源结构策略调整以减缓温室效应、合理利用资源、保护环境的切实可行的途径。     

Status of Integrated IHX/Pump Development for JSFR

This paper illuminates the status of research and development on the integrated IHX/Pump concept. The integrated IHX/Pump is the incorporated component of the intermediate heat exchanger (IHX) and the primary pump. Among the innovative technologies of the Japan Sodium-Cooled Fast Reactor (JSFR) in the Fast Reactor Cycle Technology Development (FaCT) project, the integrated IHX/Pump concept is one of the major innovative ideas for plant economy by reducing the amount of material in the primary cooling system and the building volume. This report summarizes the view of the integrated IHX/Pump, a development plan, evaluation methods, and the present test results with the 1/4-scale IHX/Pump test device.