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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Non-Destructive post-irradiation examination results of the first modern fueled experiments in TREAT
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Non-Destructive post-irradiation examination results of the first modern fueled experiments in TREAT

机译：未破坏性辐照检查结果，其第一个现代燃料实验治疗

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A series of experiments were conducted in the Transient Reactor Test (TREAT) Facility as part of commissioning for nuclear fuel safety research to be continued over the next several decades. TREAT was first constructed in the late 1950s to support research on nuclear fuel specimens under extreme nuclear-heated conditions. Following a decades-long hiatus, reactor operations were resumed at TREAT in 2017 to support the reemerging field of fuel-safety research. The first fueled tests were performed on fresh light-water reactor (LWR)-type sub length specimens (4.9% enriched UO2 in zirconium-alloy cladding) in inert gas capsules with the primary objective to demonstrate new irradiation capabilities, including calculation of energy-coupling factor, and to provide a baseline reference for interpretation of future experiments on accident tolerant fuel designs and high burnup standard fuels. In parallel, several new nondestructive post-irradiation experimental systems and processes have been developed and were successfully demonstrated using these samples. Five capsules were irradiated with energy injections and peak cladding temperatures of similar to 212 and similar to 1312 J/gUO(2) and similar to 561 similar to 2113 degrees C, respectively. These irradiations resulted in various degrees of fuel damage that were characterized using advanced non-destructive examinations. The post-irradiation examinations highlighted that, in the most-energetic transient, zirconium breakout, also referred to as 'candling,' was observed as gross cladding melting and relocation. Post-irradiation examinations also confirmed results inferred from in situ instrumentation during irradiation and are consistent with previous results from other studies. (C) 2020 Elsevier B.V. All rights reserved.
机译：在瞬态反应器测试（治疗）设施中进行了一系列实验，作为核燃料安全研究的一部分，在未来几十年中继续进行。在20世纪50世纪50年代后期首次构建了治疗，以支持核燃料标本在极端核激励条件下的研究。在几十年的人口中，2017年恢复了反应堆业务，以支持再次燃料安全研究领域。在惰性气体胶囊中对新鲜光 - 水反应器（LWR）型亚长度试样（4.9％富集UO2）进行第一种燃料试验在惰性气体胶囊中，主要目的是展示新的辐照能力，包括计算能量 - 耦合因子，为解释未来实验对事故耐性燃料设计和高燃烧标准燃料的基准引用。并行地，已经开发出了几种新的非破坏性辐射实验系统和工艺，并使用这些样品成功地证明了。用能量注射和峰值包层温度照射五个胶囊，与212相似，类似于1312 j / guo（2），类似于类似于2113℃的561。这些照射导致使用先进的非破坏性检查的特征在于各种燃料损伤。辐照后检查强调，在最具活力的瞬态锆突破，也被称为“蜡烛”，被认为是总包层熔化和搬迁。辐照后检查还确认了在辐照期间从原位仪器推断的结果，并与其他研究的先前结果一致。 （c）2020 Elsevier B.v.保留所有权利。

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