Experimental and numerical study of the dynamics at the fuel rod/spacer grid interface in nuclear reactors

核反应堆燃料棒/定位栅格界面动力学的实验和数值研究

• 批准号: 530933-2018
• 负责人: Amabili, Marco
• 金额: $ 1.82万
• 依托单位: McGill University
• 依托单位国家: 加拿大
• 项目类别: Collaborative Research and Development Grants
• 财政年份: 2021
• 资助国家: 加拿大
• 起止时间: 2021-01-01 至 2022-12-31
• 项目状态: 已结题
• 来源: https://www.nserc-crsng.gc.ca/ase-oro/Details-Detailles_eng.asp?id=719671
• 关键词: Experimental; numerical; study; dynamics; fuel

Flow-Induced Vibrations (FIV) found in the Pressurized Water Reactors (PWR) cause fretting wear on critical fuel assembly components, including fuel rods. Fuel rods are long slender tubes made of Zirconium alloy which contain the nuclear fuel and act as the barrier between nuclear fission products and the external environment. Excessive wear in the fuel rods' surface could break this safety barrier and release fission products into the external environment. Thus understanding this fretting phenomenon and developing methodologies to predict the severity is of critical importance to FIV and fretting experts at Framatome Canada Ltd. As this helps them to ensure not only the safety and performance of the fuel components but also reduce costs in manufacturing the same. Specifically, the fretting wear is attributed to the relative motion between the fuel rod and the support. There is no established methodology to experimentally measure this relative motion between them. An accurate measurement of this phenomenon would help FIV experts in validating their fretting models and accurately predicting the impact of fretting wear on the fuel components. The proposed project pertains to the safety and structural integrity of fuel rods subjected to flow-induced vibrations by developing an innovative test methodology to track the relative displacements of the fuel rods surface (point of contact) and the spacer grid surface (point of contact) and the net force exchange between the two surfaces during flow-induced vibrations of the fuel rod. In addition, a theoretical methodology to describe the evolution of the boundary conditions at the fuel rod-spacer grid interface will be developed to better understand the effect of interface conditions on the structural stability of the fuel rod during its dynamic response when subjected to flow-induced vibrations. The proposed project is a continuation of a number of successful collaborations between McGill and Framatome Canada Ltd. (formerly AREVA NP Canada Ltd.) under the NSERC grants such as NSERC-EG#462720-14, NSERCEGplus#476586-14 and NSERC-CRDPJ #490978-15.

在加压水反应堆（PWR）中发现的流动诱导的振动（FIV）导致关键燃料组件组件（包括燃料棒）上的插图磨损。燃料棒是由锆合金制成的长长管，其中包含核燃料，并充当核裂变产品与外部环境之间的障碍。燃油杆表面过多的磨损可能会破坏此安全性屏障并将裂变产品释放到外部环境中。因此，了解这种烦恼现象并开发方法来预测严重性对于Framatome Canada Ltd的FIV和烦恼专家至关重要。因为这有助于他们确保不仅确保燃料组件的安全性和性能，而且还可以降低制造成本。具体而言，插图磨损归因于燃油棒和支撑之间的相对运动。没有建立的方法可以实验测量它们之间的相对运动。对这种现象的准确测量将有助于FIV专家验证其壁板模型，并准确预测刷子磨损对燃料组件的影响。拟议的项目与通过开发创新的测试方法来跟踪燃料杆表面（接触点）和间隔网（接触点）（接触点）（接触点）和在燃油杆流动振动过程中两个表面之间的净力交换来跟踪燃油棒的安全性和结构完整性。此外，将开发一种理论方法来描述燃料杆杆间距界面处边界条件的演变，以更好地了解界面条件对燃料杆在其动态响应过程中的结构稳定性的影响，当受到流动诱导的振动时。拟议的项目是McGill和Framatome Canada Ltd.（以前是Areva NP Canada Ltd.）之间的许多成功合作，例如NSERC赠款，例如NSERC-EG＃462720-14，NserceGplus＃476586-14和NSERC-CRDPJ＃4909090978-15。