Session: 07-13: SMR and Advanced Reactors - II

Paper Number: 134758

134758 - Effect of Corrosion Behavior on the Heat Transfer Performance of Fuel Cladding in Lead-Cooled Fast Reactors 

Abstract: 

In lead-cooled fast reactors, materials like stainless steel are highly susceptible to corrosion by liquid metal. One method to prevent corrosion in lead/lead-bismuth systems is to create and maintain a protective oxide film on the surface of the stainless steel. The formation and longevity of this protective film depend on factors such as oxygen concentration, temperature, and corrosion products in the liquid metal. However, during high-oxygen concentration operation or even normal operation, the presence of this oxide film may lead to a deterioration in the heat transfer performance of the cladding. This paper addresses the effect of corrosion on heat transfer, a topic that has received little attention in the past despite its importance to fuel cladding.

The deterioration is attributed to oxidation products that form on heat transfer surfaces exposed to liquid metal. The objective is to obtain qualitative and quantitative information on the oxidation effects on heat transfer, which occurs in lead-cooled fast reactors using oxygen as a means of corrosion mitigation to prevent corrosion of fuel cladding. The primary focus will be on steady-state conditions, examining temperature variations along the axial and radial directions in the presence and absence of corrosion. This comparative analysis will provide insights into the extent of corrosion's impact on the heat transfer system.

Initially, under steady-state conditions, we will scrutinize the specific effects of corrosion behavior on the temperature distribution of fuel and cladding. By systematically observing temperature changes in scenarios with and without corrosion, a better understanding of the balance between oxide film formation and heat conduction can be attained. Additionally, emphasis will be placed on analyzing temperature changes radially to gain a comprehensive understanding of the influence of corrosion behavior on the cladding surface.

Furthermore, an analysis will be conducted under accident conditions to assess the potential threats posed by cladding corrosion to lead-cooled fast reactor’s safety. Simulating temperature changes in various accident scenarios will enable an evaluation of the response of corrosion behavior under abnormal conditions, providing a practical understanding of its actual impact during reactor operation.

In summary, this study aims to provide a comprehensive understanding of the impact of cladding corrosion behavior on heat transfer performance in lead-cooled fast reactors. Such insights will contribute valuable support for enhancing the design and operation of cooling systems, ensuring the safety and reliability of nuclear energy systems. This research is crucial for advancing the development of future lead-cooled fast reactors.

Presenting Author: Wenpei Feng Chengdu University of Technology

Presenting Author Biography: Dr. Feng is a dedicated researcher currently serving as a Researcher at Chengdu University of Technology. With a focus on corrosion behavior in lead-cooled fast reactors and expertise in multi-physics and multiscale coupling analysis, Dr. Feng has contributed significantly to the field. Driven by a passion for advancing nuclear technology, Dr. Feng continues to make valuable contributions to the understanding of corrosion phenomena and its implications.

Authors:

Wenpei Feng Chengdu University of Technology
Shangdong Yang Chengdu University of Technology
Hongxing Yu Nuclear Power Institute of China
Xingqing Lu Chengdu University of Tehnology
Xue Zhang Nuclear Power Institute of China
Zhixing Gu Chengdu University of Technology