Development and verification of control rod performance analysis code COTTON

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Authors: Kaiyuan WANG, Shengzhi YANG, Xiaoyan WEI, Zhongcun Chen, Xin JIN
Cited by: 0
References: 10

Abstract

BackgroundThe control rod is mainly composed of neutron absorber, stainless steel cladding and absorber spring. During reactor operation, control rods modulate the reactor's power output by absorbing neutrons through the absorber, thereby ensuring its safe operation.PurposeThis study aims to develop and verify a 1.5-dimensional control rod performance analysis software, named as COTTON, used to simulate the performance change process of control rods under the action of heat and radiation in the reactor.MethodsFirst of all, a set of basic theoretical models, such as thermal analysis model, mechanical calculation model, internal pressure model and spring model, was established to analyze the radiation behavior of control rods with COTTON code. In particular, the integral thermal conductivity method and the mechanical transfer matrix algorithm were established for heat transfer and stress-strain calculation respectively. Then, the method of time discretization and space discretization were used to complete the software development, and the multidimensional analysis of the control rod at different times and different positions in its life cycle was realized. Finally, the validation assessment was conducted using pool-side inspection data from nuclear power plants by China Nuclear Power Technology Research Institute.ResultsBased on the operation example of nuclear power plant, the results show that the predicted values meet the design requirements. The temperature of the absorber and the cladding temperature are lower than the melting point, especially the temperature margin of the absorber is 393.9 ℃. The predicted value (P) of cladding diameter is in good agreement with the experiment data (M), the mean value of M/P is 0.992, and the standard deviation of M/P is 0.003.ConclusionsThe COTTON code proposed in this study integrates comprehensive functionality for analyzing control rod performance, offering technical support for both the mechanical design and operational processes.

Fields of Study & Subjects

Nuclear Materials and Properties Nuclear and radioactivity studies Nuclear reactor physics and engineering

Publication details

Journal / source
Nuclear Techniques
Volume
49
Issue
1
Pages
010601–010601
Publication date
1 January 2026
Language
EN