HTR-10燃料元件的制造和发展趋势

经过二十多年的研究和发展,研制成功了具有我国自主知识产权的高温气冷堆燃料元件制造技术,为10MW高温气冷堆生产了产炉燃料元件.生产的燃料元件所有性能指标均满足设计要求,平均制造破损率为4.7×10-5,达到了世界先进水平.为了考验燃料元件在堆内正常工况和事故工况下的辐照性能,分别从第一和第二批产品中各取出两个燃料球进行了辐照考验.辐照试验在俄罗斯IVV-2M堆进行,最高燃耗和累积快中子通量分别达到了107000MWd/t(U)和1.31×1021n/cm2,辐照没有引起燃料元件中包覆燃料颗粒的破损.为了满足超高温气冷堆的运行要求,新的ZrC"TRISO"型颗粒燃料有可能代替传统的SiC "TRISO"型颗粒燃料.     

秦山核电厂燃料元件内辐照考验的分析和评价

为了验证秦山核电厂燃料元件的堆内性能,在重水试验堆开展了3×3-2小元件堆内综合辐照考验。本文就影响考验结果的若干技术问题和考验条件进行了仔细的分析,充分论证了该试验具有的实际意义。考验件在堆内经历了相当电厂堆稳态工况和一般事故工况的考验。 考验棒最大燃耗达34GWd/tU,棒最大表面热负荷达1.39MW/m~2。在整个考验过程中没有发生考验棒的破损。文章最后就考验结果在验证燃料元件性能及其在电厂堆内安全可靠运行方面进行了评价。     

秦山核电厂燃料元件堆内辐照考验的分析和评价

为了验证秦山核电厂燃料元件的堆内性能,在重水试验难开展了3×3—2小元件堆内综合辐照考验。本文就影响考验结果的若干技术问题和考验条件进行了仔细的分析,充分论证了该试验具有的实际意义。考验件在堆内经历了相当电厂堆稳态工况和一般事故工况的考验。考验棒最大燃耗达34GWd/tU,棒最大表面热负荷达1.39MW/m_2。在整个考验过程中没有发生考验棒的破损。文章最后就考验结果在验证燃料元件性能及其在电厂堆内安全可靠运行方面进行了评价。     

HFETR堆内燃料元件吊装万向工具研制

描述了高通量工程试验堆（简称ＨＦＥＴＲ）堆内燃料元件吊装万向工具研制的原因，该工具的结构，原理，特点及其在ＨＦＥＴＲ堆内燃料元件吊运中的意义。     

高性能燃料元件堆内试验组件焊接技术

高性能燃料元件研究项目组设计的堆内试验组件的焊接部件主要包括:1mm厚的不锈钢燃料包壳管和压力包壳管（合称为双包壳管）、端塞及压力传感器等。焊接设计要求达到以下标准:熔深1mm;焊缝变形量小于0.1mm的双包壳管间隙;焊缝氦漏率小于10-5Pa·m3/s:需要通过按1级焊缝标准要求的X光无损检测。根据任务要求,我们将高性能燃料元件堆内试验组件的焊接分为元件本身结构的焊接和堆内试验测试系统与元件结构的焊接两个部分。 元件本身构件的焊接主要是指元件的双包壳薄壁管与端塞的焊接和端塞的充压堵孔焊。这部     

高通量工程试验堆堆芯燃料元件温度和流量测量

论述了高通量工程试验堆堆芯燃料元件的温度-流量测量装置及其测量系统,论述了在反应堆提升功率、首炉全寿期运行试验和第二炉加深元件燃耗试验中仪表燃料元件在稳态与动态测试方面的应用情况,论述了确定肋下热点温度的方法,进行了误差分析,介绍了燃料元件出堆脱水试验。该测量装置成功地用于高通量堆的高功率、深燃耗安全运行,燃料元件 随堆辐照及各种试验研究。装有本测量装置的仪表燃料元件经过两炉运行,积分功率达到9088MWd,最大点燃耗约为64.9%,从而大大提高了高通量堆燃料使用的经济性。     

10 MW高温气冷堆燃料元件辐照后检验

为了评价10 MW高温气冷堆(HTR-10)用燃料元件的性能,从第1和第2生产批次中分别随机抽取两个球形燃料元件进行辐照考验.辐照考验在俄罗斯的IVV-2M堆内进行,采用动态辐照试验的方法,可分别控制每个辐照盒中燃料元件的温度和测量气态裂变产物的释放.辐照后检验包括外观检查、尺寸测量、固体裂变产物在基体石墨内的分布测量、包覆燃料颗粒破损率测量和金相观察.辐照后检验结果表明辐照没有引起燃料元件中包覆燃料颗粒的破损, 生产的燃料元件满足10 MW高温气冷堆的设计要求.     

燃料元件堆内瞬态行为试验研究工作进展

燃料元件堆内瞬态行为试验研究工作进展@黄玉才@张培升     

Zr-2包壳管爆破力学性能

核燃料元件是反应堆的核心部件，由燃料芯块、包壳及其构件组成。由于燃料元件的运行环境比较恶劣，中子辐照、冷却剂的腐蚀及在开堆、停堆、和运行后期燃料芯块与包壳的机械相互作用和裂变气体产物的释放，使包壳管承受双向应力，均会造成燃料元件的力学性能下降，形成安全隐患，它的安全性能直接影响反应堆的安全可靠性。为更好地模拟包壳在堆内的受力状态，一般采用内压爆破试验来获得包壳材料的断裂强度与延性数据。     

卡尔斯鲁厄核研究中心试验快堆环状元件

【联邦德国《原子经济》1984年第4期第186页报道】目前在卡尔斯鲁厄核研究中心的试验快堆核电站KNK-Ⅱ上,正在试验一种全新的环状燃料元件。它的燃料棒内充填了碳化铀和碳化钚的混合物。这种增殖堆燃料元件可以达到很高的功率密度。因而     

Criteria for Optimizing Technical Solutions for NPP

Atomic Energy - Criteria for optimizing technical solutions in designing and modernizing NPP are considered. Based on their analysis, it is shown that it is economically efficient to increase the...     

Need for and requirements for a neutron irradiation facility for fusion materials testing

The construction and operation of an intense 14-MeV neutron source is essential for the development and eventual qualification of structural materials for a fusion reactor demonstration plant (DEMO). Because of the time required for materials development and the scale-up of materials to commercial production, a decision to build a neutron source should precede engineering design activities for a DEMO by at least 20 years. The characteristic features of 14-MeV neutron damage are summarized including effects related to cascade structure, transmutation production, and dose rate. The importance of a 14-MeV neutron source for addressing fundamental radiation damage issues, alloy development activities, and the development of an engineering database is discussed. For these considerations, the basic requirements and machine parameters are derived.     

地震工况下设备土建载荷的计算方法

在设备抗震分析中,设备对基础的作用力是土建设计时所需的重要参数。本文根据不同的工程实例,给出2种设备在地震工况下土建载荷的计算方法,即简便方法和谱分析计算中的刚性区域法,并给出了算例。     

Experimental Results for an Acoustic Driver for MTF

General Fusion is planning to form an FRC or spheromak of 10¹⁷ cm⁻³, 100 eV, 40 cm diameter by merging two spheromaks with reverse or co-helicity. This target will be further compressed in a 3 m diameter tank filled with liquid PbLi with the plasma in the center. The tank is surrounded with pneumatically powered impact pistons that will send a convergent shock wave in the liquid to compress the plasma to 10²⁰ cm⁻³, 10 keV, 4 cm diameter for 7 μs. General Fusion has built a 500 kJ, 80 μs, 6 GW pneumatic impact piston capable of developing 2 GPa (300 kpsi). In this paper we will present the performances achieved to date.     

Principles for Finding Matrices for Immobilizing High-Level Wastes

The principles for selecting matrices for immobilizing high-level wastes are examined. It is concluded that actinides should be separated and embeeded in the matrix separately from fission products. The minimum significant specific activity, regulated by NRB-99, cannot be used to estimate the storage time. It is suggested that such values be established as a function of the leach rate of radionuclides and matrix materials from matrices. For this, a standard leaching method using pulverized materials must be specified. Two criteria are proposed for comparing matrix materials.     

Software for gamma cameras for mapping radioactive contamination

The software for portable systems for obtaining γ image with coding apertures (masks) is described. The software developed controls all systems that form an image and obtain shadow patterns, reconstructs the initial γ-image, and processes previously obtained images. The software is used with portable systems in which URA and MURA type masks with different rank are used as the coding aperture. Programs for modeling the process of obtaining shadow patterns using real apparatus which has different positionsensitive detectors are described. Possible configurations of new apparatus which could be of practical interest are examined.     

Basis for developing samarium AMS for fuel cycle analysis

Modeling of nuclear reactor fuel burnup indicates that the production of samarium isotopes can vary significantly with reactor type and fuel cycle. The isotopic concentrations of ¹⁴⁶Sm, ¹⁴⁹Sm, and ¹⁵¹Sm are potential signatures of fuel reprocessing, if analytical techniques can overcome the inherent challenges of lanthanide chemistry, isobaric interferences, and mass/charge interferences. We review the current limitations in measurement of the target samarium isotopes and describe potential approaches for developing Sm-AMS. AMS sample form and preparation chemistry will be discussed as well as possible spectrometer operating conditions.