Development and Verification of Reactor Core Transient Coupling Simulation Software CTSS

Pan Junjie; An Ping; Wang Wei; Zhao Wenbo; Xing Suo; Lu Wei; Chai Xiaoming

doi:10.13832/j.jnpe.2018.02.0137

Volume 39 Issue 2

Feb. 2025

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Pan Junjie, An Ping, Wang Wei, Zhao Wenbo, Xing Suo, Lu Wei, Chai Xiaoming. Development and Verification of Reactor Core Transient Coupling Simulation Software CTSS[J]. Nuclear Power Engineering, 2018, 39(2): 137-141. doi: 10.13832/j.jnpe.2018.02.0137

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Pan Junjie, An Ping, Wang Wei, Zhao Wenbo, Xing Suo, Lu Wei, Chai Xiaoming. Development and Verification of Reactor Core Transient Coupling Simulation Software CTSS[J]. Nuclear Power Engineering, 2018, 39(2): 137-141. doi: 10.13832/j.jnpe.2018.02.0137

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Development and Verification of Reactor Core Transient Coupling Simulation Software CTSS

doi: 10.13832/j.jnpe.2018.02.0137

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institution of China, Chengdu, 610213, China

Received Date: 2017-12-20
Rev Recd Date: 2018-01-18

Available Online: 2025-02-09

Abstract

Abstract

Reactor Core Transient Simulation Software（CTSS V1.0）,which is coupled by 3 D space-time kinetic program NACK V1.0,CORe Thermal-Hydraulic analysis program（CORTH V2.0） and Fuel Rod Performance Analysis Code（FUPAC V1.1）,is used to simulate the typical PWR core.NACK V1.0 calculates the core diffusion equations with coarse node method and provides core power distribution for sub-channel model and fuel analysis model.CORTH V2.0 describes the core as a series of connected or unconnected sunchannel to calculate the coolant temperature.FUPAC V1.1 is used to simulate the thermodynamic behavior of fuel rod and calculate the fuel rod temperature.The calculation of PWR benchmark problem NEACRP-L-335 shows that CTSS is in good agreement with benchmark program PARCS.
- Reactor core transient couple,
- CTSS,
- PWR benchmark problem,
- NEACRP-L-335