Discussion on the sizing method of low voltage power cables for SMR

This paper analyzes the Small Modular Reactor (SMR) nuclear power plant low-voltage power cables in different application environments of the baseline current-carrying capacity determination, current-carrying capacity correction, cable cross-section selection, cable cross-section calibration of the principles and methods, as well as the use of standards. Focus on comparative analysis of low-voltage cables in the bridge randomly filled with laying to determine the method of load capacity, small piles according to the bridge filling rate is not the same, the allowable heat is not consistent, according to the different allowable heat determines a different cross-section of the cable in different filling rates under the load capacity, and the national standard is based on the number of layers of the cable to determine the load capacity correction coefficients, respectively, applicable to the different methods of laying. Finally, a flow chart gives the cable application environment to determine the cable cross-section selection and cable cross-section calibration of the process followed, for the subsequent nuclear power engineering design and improvement provides a reference.

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Publication Details

Published
2024-12-12
DOI
https://doi.org/10.1117/12.3050372
Primary Topic
Thermal Analysis in Power Transmission
Type
article
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article

Discussion on the sizing method of low voltage power cables for SMR

Bowen Jiang, Yang Li
Thermal Analysis in Power Transmission
article

Discussion on the sizing method of low voltage power cables for SMR

Bowen Jiang, Yang Li
article en

Abstract

This paper analyzes the Small Modular Reactor (SMR) nuclear power plant low-voltage power cables in different application environments of the baseline current-carrying capacity determination, current-carrying capacity correction, cable cross-section selection, cable cross-section calibration of the principles and methods, as well as the use of standards. Focus on comparative analysis of low-voltage cables in the bridge randomly filled with laying to determine the method of load capacity, small piles according to the bridge filling rate is not the same, the allowable heat is not consistent, according to the different allowable heat determines a different cross-section of the cable in different filling rates under the load capacity, and the national standard is based on the number of layers of the cable to determine the load capacity correction coefficients, respectively, applicable to the different methods of laying. Finally, a flow chart gives the cable application environment to determine the cable cross-section selection and cable cross-section calibration of the process followed, for the subsequent nuclear power engineering design and improvement provides a reference.

China General Nuclear Power Corporation (China) (CN)
Affordable and clean energy
Openalex Percentile: Top 73%
Thermal Analysis in Power Transmission
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