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A Study of Mechanical Integrity of Coated Particle Fuel under High Burnup Irradiation

机译:高燃烧辐照下涂层粒子燃料机械完整性研究

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In high temperature gas-cooled reactors (HTGRs), Tri-isotropic (TRISO)-coated fuel particles are employed as fuel. The TRISO coatings consist of a low-density, porous pyrolytic carbon (PyC) buffer layer adjacent to the spherical fuel kernel, followed by an isotropic PyC layer (inner PyC; IPyC), a silicon carbide (SIC) layer and a final PyC (outer PyC; OPyC) layer. In safety design of the HTGR fuels, it is important to retain fission products within particles so that their release to primary coolant does not exceed an acceptable level. From this point of view, the basic design criteria for the fuel are to prevent significant additional fuel failures during operation. In order to investigate fuel behavior under high burnup condition, irradiation tests were performed. The irradiation tests were carried out independently as 91F-1A capsule (at the Japan Materials Testing Reactor of Japan Atomic Energy Research 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 to 10%FIMA (% fission per initial metallic atom). In order to keep fuel integrity up to high burnup, thickness of buffer and SiC layers of the high burnup fuel particle were increased. During irradiation, fuel performance was monitored by 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 coating layers due to the internal pressure of fission gases and CO gas with burnup. The result showed that no tensile stresses acted on the SiC layers even at the end of irradiation and no pressure vessel failure occurred in the intact particles. This result implies that there were weak particles and they failed to the through-coatings failure during irradiation. The weak particles correspond to particles with defect in the SiC layer. The SiC-defected particle would be the particle with micro crack on the SiC layer surface. Since the high burnup fuel compact was high packing fraction, i.e., contained much coated fuel particles, to keep fissile materials, contact of the coated fuel particles would occur in fuel compaction process.
机译:在高温气体冷却反应器(HTGR)中,使用三位同学(Triso)涂覆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,其次是各向同性的PYC层(内部PYC; IPYC),碳化硅(SIC)层和最终PYC(外部pyc; opyc)层。在HTGR燃料的安全设计中,重要的是保留颗粒内的裂变产品,使其对初级冷却剂的释放不超过可接受的水平。从这个角度来看,燃料的基本设计标准是在运行期间防止有着重要的额外燃料失效。为了在高燃烧条件下调查燃料行为,进行辐照测试。照射试验独立于91F-1A胶囊(日本原子能研究机构的日本材料测试反应器)和HRB-22胶囊(在橡木岭国家实验室的高通量同位素反应器中)照射试验。照射试验的燃料被称为高燃烧燃料,其靶燃烧为5至10%FIMA(每初始金属原子%裂变)。为了使燃料完整性保持高燃烧,高燃烧燃料粒子的缓冲液和SiC层的厚度增加。在照射期间,通过扫描气体中的裂变气体浓度监测燃料性能。在两种照射试验中观察到涂覆颗粒的失败。通过压力容器故障模型分析燃料失效行为,这是由于燃烧气体内部压力和燃烧的碳气的内部压力评价涂层的失效概率。结果表明,即使在照射的结束时也没有在SiC层上作用的拉伸应力,并且在完整的颗粒中没有发生压力容器失效。该结果意味着存在薄弱的颗粒,并且在照射期间未能涂层失效。弱颗粒对应于SiC层中具有缺陷的颗粒。 SiC缺陷的颗粒是SiC层表面上具有微裂纹的颗粒。由于高燃烧的燃料紧凑件高填充馏分,即含有多大涂覆的燃料颗粒,以保持裂变材料,燃料压实过程中将发生涂覆的燃料颗粒的接触。

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