高温气冷堆环境模拟装置动态传热特性建模分析

清华大学核能与新能源技术研究院研制了模拟高温气冷堆温度、环境氛围的材料测试装置,可进行1 600℃及以下高温碳还原环境下的各类实验。通过对该实验装置的结构进行适当简化,建立了模拟其高温、真空条件下辐射、导热动态传热特性的二维数学模型。仿真结果与实验装置各测点的实测温度变化趋势一致,可解释实验时观察到的多种动态传热现象。此外,该模型可对材料测试区径向温度分布、不同加热功率条件下发热体最高温度等难以直接测量的重要参数进行估计,给出进一步实验的指导性建议。     

球床式高温气冷堆球流及球床辐射的理论与实验研究进展

球床堆芯的球流及等效导热系数是直接影响球床式高温气冷堆设计、运行和安全的重要依据,具有重要的意义。清华大学核能与新能源技术研究院近年对球流和球床等效导热系数进行了实验测量、理论研究和数值模拟,全面深入地揭示了球流规律、球流纺及径向内扩散规律、球床几何优化、物性参数影响、球流流态表征及刻画、球床等效导热系数建模等。本文对此进行了回顾总结,并指出了下一步的研究方向。     

高温堆球床等效导热系数实验温度测量系统设计

为解决清华大学核能与新能源技术研究院研制的高温堆示范电站(HTR-PM)堆芯全尺寸球床等效导热系数测量实验装置中温度场的稳定、准确测量问题,本文设计并构建了其测温系统的软硬件系统。该装置中的温度测量涉及高温堆安全分析的全部温度范围(0~1 600℃),并处于石墨球床环境中。根据实验装置的总体构成和测点布置需求,选择了特殊工艺制作的非标准钨铼热电偶作为前端传感器,搭建了基于NI PXI平台的数据采集硬件系统,采用生产者/消费者模式和队列模式结合的方式编写了软件系统。用前期缩小比例的验证装置对材料、结构、设备等关键设计进行先期验证,结果表明,设计的温度测量系统可长期稳定、可靠满足实验的测温需求,为球床等效导热系数实验研究的开展、提升高温气冷堆经济性和安全性奠定了基础。     

高温气冷球床堆有效导热系数模型的改进

有效导热系数是高温气冷球床堆热工设计和安全分析程序中的基本参数,ZBS模型广泛应用于球床结构有效导热系数的预测。本文针对ZBS模型中的关键经验型参数——接触面积系数φ进行了分析,通过对不同堆积结构球床有效导热系数的数值分析,获得了12组接触直径比和配位数及其对应的φ值,然后通过多元线性分析获得φ的计算公式。与德国SANA实验结果进行比较,发现改进后的ZBS模型预测能力优于其他模型。改进后的ZBS模型的计算结果与先前实验测量的球床主体区域的有效导热系数吻合也很好。本文研究结果可为高温气冷球床堆的设计和安全分析提供理论支持。     

高温气冷堆环境模拟装置热电偶信号波动问题研究

清华大学核能与新能源技术研究院研制了模拟高温气冷堆堆内温度、环境氛围的材料测试装置,可进行1 600℃及以下高温碳还原环境下的各类实验。实验装置的中心大电流加热产生的强电磁场对测试区内的热电偶温度信号施加了很大的干扰,使温度信号附加了幅度达几十度的高频无规则波动。基于NI高速同步采集技术,进行了信号干扰的分析实验,明确了干扰源及干扰途径。本文针对干扰信号的自身规律,提出了相应的软件抗干扰措施,较好地解决了高温堆环境模拟装置中的热电偶信号波动问题,保证了测试区内温度的精确稳定控制及测量。     

高温气冷堆球床有效导热系数的计算模型及其在SANA基准试验分析中的应用

用THERMIX程序计算了石墨球床的温度分布。研究了高温气冷堆球床内部热量传递机制,给出了三种有效导热系数的分析方法和计算模型。以国际原子能机构(IAEA)关于“高温气冷堆在事故工况下的热传输和余热载出”问题的合作研究计划(Coordinated Research Program简称CRP)的SANA基准试验为基础,计算了球床内的温度分布和自然对流对传热的影响。计算结果与实验测量结果作了比较,证实了THERMIX程序和有效导热系数的准确性。     

碳纤维复合材料薄壁圆筒的轴向导热系数测试

碳纤维复合材料薄壁圆筒为各向异性导热,其轴向导热系数是筒体温度场理论计算、成型工艺优化的重要参数。碳纤维复合材料圆筒由于较小的截面面积给筒体加热、热量有效传递带来了较大困难。本文以平板材料导热系数的稳态法测试国家标准为基础,基于傅里叶一维稳态导热原理,设计了一套用于薄壁圆筒轴向导热系数测试的装置,采用双试件对称加热、辐射换热防护及热对流环境控制等实现了热量沿筒体轴向的有效传导,利用该装置对导热系数已知的铝筒进行测试,验证了该装置设计的可行性,得到了碳纤维复合材料薄壁圆筒的轴向导热系数为（4.60±0.13） W/(m•K)。     

球床式高温气冷堆球流及球床辐射的理论与实验研究进展

球床堆芯的球流及等效导热系数是直接影响球床式高温气冷堆设计、运行和安全的重要依据,具有重要的意义。清华大学核能与新能源技术研究院近年对球流和球床等效导热系数进行了实验测量、理论研究和数值模拟,全面深入地揭示了球流规律、球流纺及径向内扩散规律、球床几何优化、物性参数影响、球流流态表征及刻画、球床等效导热系数建模等。本文对此进行了回顾总结,并指出了下一步的研究方向。     

高温气冷堆联合循环技术潜力研究

模块式高温气冷堆与燃气联合循环发电分别代表着当今核能界和常规发电界的最先进技术,两者的结合为提高核电的安全性和经济性提供了一条新的思路,是一个极具竞争优势的选择方案。本文通过分析高温气冷堆和联合循环的现状及发展趋势,着重从今后10～20年技术潜力的角度研究高温气冷堆联合循环技术,并给出各种堆芯出口温度条件下的循环方案。例如,堆芯出口温度为1050℃,循环效率可达51.4%。     

200 MW 模块式高温气冷堆回热循环系统热力学设计研究

高温气冷堆是一种新型的反应堆堆型,它可以提供高达900 ℃的高品质热源,为了充分利用这一资源,需要在核能利用中引入气体轮机这一常规工业中的先进技术.给出了200 MW 高温气冷堆的气体轮机回热循环系统的设计研究.     

模块式高温气冷堆非能动余热排出系统分析与研究

非能动的余热排出系统是高温气冷堆固有安全性的重要体现之一。本文介绍了模块式高温气冷堆余热排出系统热工水力计算方法,并给出了不同工况、不同环境温度下余热排出系统的运行参数,为余热排出系统的设计和运行提供了参考。对事故工况下舱室混凝土温度分布进行了数值分析,结果表明混凝土最高温度低于安全限值。     

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。     

The Computation of Doppler-Broadened Functions

A method for simultaneously measuring thermal diffusivity and specific heat has been developed from a previously proposed method, devised for measuring the thermal diffusivity of materials by means of samples in the form of small solid discs which are heated stepwise.

The disc is placed in a vacuum furnace and heated on one surface by light, whose intensity is varied in steps. The resulting temperature rise reaching the other surface of the sample is recorded, from which the thermal diffusivity and the specific heat are both determined. The values obtained serve, in turn, to yield the thermal conductivity. An apparatus utilizing this principle has been devised, with which a nickel specimen was measured in the ranging from the room temperature to 1,300°K.     

Calcium oxide/carbon dioxide reactivity in a packed bed reactor of a chemical heat pump for high-temperature gas reactors

The thermal performance of a chemical heat pump that uses a calcium oxide/carbon dioxide reaction system was discussed as a heat storage system for utilizing heat output from high temperature gas reactors (HTGR). Calcium oxide/carbon dioxide reactivity for the heat pump was measured using a packed bed reactor containing 1.0 kg of reactant. The reactor was capable of storing heat at 900 °C by decarbonation of calcium carbonate and generating up to 997 °C by carbonation of calcium oxide. The amount of stored heat in the reactor was 800–900 kJ kg⁻¹. The output temperature of the reactor could be controlled by regulating the carbonation pressure. The thermal storage performance of the reactor was superior to that of conventional sensible heat storage systems. A heat pump using this CaO/CO₂ reactor is expected to contribute to thermal load leveling and to realize highly efficient utilization of HTGR output due to the high heat storage density and high-quality temperature output of the heat pump.     

高温蒸汽电解制氢系统温度敏感性分析

通过电化学方法建立高温蒸汽电解制氢系统温度敏感性分析的数学模型,通过该模型对系统温度敏感性进行分析,并提出温度敏感系数的概念。定性的研究结果表明,在不同发电效率、电解效率以及热效率下,温度敏感系数均随着工作温度的增加而增大。这表明,系统总效率随着温度的升高而增大,且随着发电效率和热效率的增加,温度敏感系数也随之增大,但电解效率对温度敏感系数影响较小。定量的研究结果表明,工作温度为750～950℃的高温蒸汽电解制氢系统的温度敏感系数约为1.40,即系统工作温度分别为800和900℃时,由于温度升高而使系统总效率分别增加约10.5%和12%;相应的实际总制氢效率可分别高达55.8%和56.5％,约是常规碱性水电解制氢效率的两倍。     

高温气冷堆螺旋管式直流蒸汽发生器热工水力学

高温气冷堆蒸汽发生器具有一次侧氦气工质、二次侧直流、螺旋管结构、工作温度高等特点,其热工水力特性与传统压水堆自然循环蒸汽发生器存在很大区别。针对高温气冷堆蒸汽发生器的特点,对其基础热工水力及特有热工水力学问题进行了阐述,主要包括螺旋管内单相及两相流阻及换热计算、横掠螺旋管束流阻及换热计算、温度均匀性及两相流不稳定性等。同时介绍了清华大学核能与新能源技术研究院针对高温气冷堆蒸汽发生器热工设计、温度均匀性及两相流不稳定性等热工水力学问题所开发的一维稳态程序、一维瞬态程序、二维分析程序和方法,并对分析结果和结论进行了讨论。相关研究方法、程序和结论对其他相似参数螺旋管和直管式直流蒸汽发生器具有参考和借鉴意义。     

Core Burnup Calculation of Plutonium Burning Inert-Matrix Fueled High Temperature Gas Cooled Reactor

For the efficient reduction of excess plutonium amount, Japan Atomic Energy Research Institute (JAERI, now Japan Atomic Energy Agency) has studied a concept of rock-like oxide (ROX) fuel as a kind of inert matrix fuel (IMF). In the JAERI study, ROX fuel is burnt in existing light water reactors (LWRs), while in this study, pebble bed type high temperature gas cooled reactor (HTGR) is studied, mainly because of its high neutron economy and softer neutron spectrum than LWRs. Here, PuO₂-yttria stabilized zirconia (YSZ: (Zr,Y)O_2-x) particles are dispersed in graphite matrix. In the ROX fueled LWR study, it was necessary to improve fuel temperature reactivity coefficients by adding such additives as ²³⁸U and Er. Here in HTGR, although the negative temperature coefficient is much larger than that in LWR without any improvements, temperature coefficient was improved as large as possible to the level of UO₂ HTGR case by adding Er in the fuel. Burnup calculations on PuO_2-YSZ fueled HTGR, by simulating the continuous refueling of fuel pebbles with the batch fuel loading, showed almost complete transmutation for ²³⁹Pu and more than 80% for the total plutonium. As the maximum power density of the fuel pebble obtained by the core burnup calculation was very large in comparison with the UO₂ HTGR, the maximum temperature in YSZ fuel particle was also evaluated. Despite the low thermal conductivity of YSZ, the evaluated YSZ temperature was well below the melting point, thanks to the high thermal conductivity of graphite and small YSZ particle size. Here, the high power density in the Pu-YSZ fueled core might become a problem, but is possible to be reduced by adjusting the initial plutonium enrichment.     

Thermal performance test of the hot gas ducts of HENDEL

A hot gas duct provided with internal thermal insulation is to be used for high-temperature gas-cooled reactors (HTGR). This type of hot gas duct has not been used so far in industrial facilities, and only a couple of tests on such a large-scale model of a hot gas duct have been conducted. The present report deals with the results of the thermal performance of the single tube type hot gas ducts which are installed as parts of a helium engineering demonstration loop (HENDEL).Uniform temperature and heat flux distribution at the surface of the duct were observed, the experimental correlations being obtained for the effective thermal conductivity of the internal thermal insulation layer. The measured temperature distribution of the pressure tube was in good agreement with the calculation by a TRUMP heat transfer computer code. The temperature distribution of the inner tube of the co-axial hot gas duct was evaluated and no hot spot was detected.These results would be very valuable for the design and development of HTGR.