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.

在压水堆（PWR）中发现的流致振动（FIV）会导致包括燃料棒在内的关键燃料组件部件的微动磨损。燃料棒是由锆合金制成的细长管，其中包含核燃料，并作为核裂变产物与外部环境之间的屏障。燃料棒表面的过度磨损可能会破坏这一安全屏障，并将裂变产物释放到外部环境中。因此，了解这种微动现象并开发预测严重程度的方法对法马通加拿大有限公司的FIV和微动专家至关重要，因为这有助于他们不仅确保燃料组件的安全性和性能，而且降低制造成本。具体地说，微动磨损归因于燃料棒和支撑件之间的相对运动。没有建立的方法来实验测量它们之间的这种相对运动。对这种现象的准确测量将有助于FIV专家验证他们的微动模型，并准确预测微动磨损对燃料组件的影响。拟议的项目涉及燃料棒的安全性和结构完整性受到流动引起的振动，通过开发一种创新的测试方法，以跟踪燃料棒表面（接触点）和定位格架表面（接触点）的相对位移和净力之间的两个表面之间的交换在燃料棒的流动引起的振动。此外，将开发一种理论方法来描述燃料棒-定位格架界面处的边界条件的演变，以更好地理解界面条件对燃料棒在受到流致振动时的动态响应期间的结构稳定性的影响。该项目是麦吉尔与法马通加拿大有限公司（原阿海珐NP加拿大有限公司）之间一系列成功合作的延续。根据NSERC赠款例如NSERC-EG#462720-14、NSERCEGplus#476586-14和NSERC-CRDPJ #490978 -15。