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A Study of Mechanical Integrity of Coated Particle Fuel under High BurnupIrradiation

机译:高燃耗辐照下包覆颗粒燃料的机械完整性研究

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In high temperature gas-cooled reactors (HTGRs), Tri-isotropic (TRISO)-coated fuel particles are employed asfuel. The TRISO coatings consist of a low-density, porous pyrolytic carbon (PyC) buffer layer adjacent to thespherical fuel kernel, followed by an isotropic PyC layer (inner PyC; IPyC), a silicon carbide (SIC) layer and a finalPyC (outer PyC; OPyC) layer. In safety design of the HTGR fuels, it is important to retain fission products withinparticles so that their release to primary coolant does not exceed an acceptable level. From this point of view, thebasic design criteria for the fuel are to prevent significant additional fuel failures during operation. In order toinvestigate fuel behavior under high burnup condition, irradiation tests were performed. The irradiation tests werecarried out independently as 91F-1A capsule (at the Japan Materials Testing Reactor of Japan Atomic EnergyResearch Institute) and HRB-22 capsule (at the High Flux Isotope Reactor of Oak Ridge National Laboratory)irradiation tests. The fuel for the irradiation tests was called high burnup fuel, whose target burnup was 5 to10%FIMA (% fission per initial metallic atom). In order to keep fuel integrity up to high burnup, thickness of bufferand SiC layers of the high burnup fuel particle were increased. During irradiation, fuel performance was monitoredby fission gas concentration in sweep gas. The failure of coated particles was observed in both irradiation tests.The fuel failure behavior was analyzed by pressure vessel failure model, which evaluate failure probability of coatinglayers due to the internal pressure of fission gases and CO gas with burnup. The result showed that no tensilestresses acted on the SiC layers even at the end of irradiation and no pressure vessel failure occurred in the intactparticles. This result implies that there were weak particles and they failed to the through-coatings failure duringirradiation. The weak particles correspond to particles with defect in the SiC layer. The SiC-defected particlewould be the particle with micro crack on the SiC layer surface. Since the high burnup fuel compact was highpacking fraction, i.e., contained much coated fuel particles, to keep fissile materials, contact of the coated fuelparticles would occur in fuel compaction process.
机译:在高温气冷堆(HTGRs)中,采用涂覆了三向同性(TRISO)的燃料颗粒作为燃料。 TRISO涂层由与球形燃料核相邻的低密度多孔热解碳(PyC)缓冲层,各向同性PyC层(内部PyC; IPyC),碳化硅(SIC)层和最终PyC(外部PyC)组成; OPyC)层。在HTGR燃料的安全设计中,重要的是将裂变产物保留在颗粒内,以使它们向主冷却剂的释放量不超过可接受的水平。从这一观点出发,燃料的基本设计标准是防止在运行过程中发生重大的附加燃料故障。为了研究高燃耗条件下的燃料行为,进行了辐射测试。辐照试验分别以91F-1A胶囊(在日本原子能研究所的日本材料试验反应堆中)和HRB-22胶囊(在橡树岭国家实验室的高通量同位素反应堆中)进行。用于辐照测试的燃料称为高燃耗燃料,其燃耗目标为5至10%FIMA(每个初始金属原子的裂变百分比)。为了保持燃料完整性直至高燃耗,增加了高燃耗燃料颗粒的缓冲层和SiC层的厚度。在辐照期间,通过扫气中裂变气体的浓度监测燃料的性能。在两次辐照试验中均观察到了涂层颗粒的失效。通过压力容器失效模型分析了燃料的失效行为,该模型评估了由于裂变气体和CO气体的内压燃烧引起的涂层失效的可能性。结果表明,即使在辐照结束时,拉伸应力也没有作用在SiC层上,并且完整颗粒中没有发生压力容器破坏。该结果表明存在弱颗粒,并且它们在辐照过程中未能通过涂层失败。弱颗粒对应于SiC层中具有缺陷的颗粒。 SiC偏转的颗粒将是在SiC层表面上具有微裂纹的颗粒。由于高燃耗的燃料压块具有高的填充率,即,含有很多被涂覆的燃料颗粒,以保持易裂变材料,因此在燃料压制过程中会发生被涂覆的燃料颗粒的接触。

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