Development of TREND dynamics code for molten salt reactors

The Molten Salt Reactor (MSR), one of the six advanced reactor types of the 4th generation nuclear energy systems, has many impressive features including economic advantages, inherent safety and nuclear non-proliferation. This paper introduces a system analysis code named TREND, which is developed a...

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Main Authors: Wen Yu, Jian Ruan, Long He, James Kendrick, Yang Zou, Hongjie Xu
Format: Article
Language:English
Published: Elsevier 2021-02-01
Series:Nuclear Engineering and Technology
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573319308046
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spelling doaj-1a1133fc5c0043038fa6b5b20daedea82021-01-22T04:49:23ZengElsevierNuclear Engineering and Technology1738-57332021-02-01532455465Development of TREND dynamics code for molten salt reactorsWen Yu0Jian Ruan1Long He2James Kendrick3Yang Zou4Hongjie Xu5Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800, China; University of Chinese Academy of Sciences, Beijing, 100049, ChinaShanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800, China; University of Chinese Academy of Sciences, Beijing, 100049, ChinaShanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800, China; University of Chinese Academy of Sciences, Beijing, 100049, ChinaDepartment of Nuclear Engineering, University of California, Berkeley, 4118, Etcheverry Hall, Berkeley, CA, 94720, USAShanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800, China; Corresponding author.Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800, ChinaThe Molten Salt Reactor (MSR), one of the six advanced reactor types of the 4th generation nuclear energy systems, has many impressive features including economic advantages, inherent safety and nuclear non-proliferation. This paper introduces a system analysis code named TREND, which is developed and used for the steady and transient simulation of MSRs. The TREND code calculates the distributions of pressure, velocity and temperature of single-phase flows by solving the conservation equations of mass, momentum and energy, along with a fluid state equation. Heat structures coupled with the fluid dynamics model is sufficient to meet the demands of modeling MSR system-level thermal-hydraulics. The core power is based on the point reactor neutron kinetics model calculated by the typical Runge-Kutta method. An incremental PID controller is inserted to adjust the operation behaviors. The verification and validation of the TREND code have been carried out in two aspects: detailed code-to-code comparison with established thermal-hydraulic system codes such as RELAP5, and validation with the experimental data from MSRE and the CIET facility (the University of California, Berkeley’s Compact Integral Effects Test facility).The results indicate that TREND can be used in analyzing the transient behaviors of MSRs and will be improved by validating with more experimental results with the support of SINAP.http://www.sciencedirect.com/science/article/pii/S1738573319308046Molten salt reactorTransient analysisCode developmentVerification and validation
collection DOAJ
language English
format Article
sources DOAJ
author Wen Yu
Jian Ruan
Long He
James Kendrick
Yang Zou
Hongjie Xu
spellingShingle Wen Yu
Jian Ruan
Long He
James Kendrick
Yang Zou
Hongjie Xu
Development of TREND dynamics code for molten salt reactors
Nuclear Engineering and Technology
Molten salt reactor
Transient analysis
Code development
Verification and validation
author_facet Wen Yu
Jian Ruan
Long He
James Kendrick
Yang Zou
Hongjie Xu
author_sort Wen Yu
title Development of TREND dynamics code for molten salt reactors
title_short Development of TREND dynamics code for molten salt reactors
title_full Development of TREND dynamics code for molten salt reactors
title_fullStr Development of TREND dynamics code for molten salt reactors
title_full_unstemmed Development of TREND dynamics code for molten salt reactors
title_sort development of trend dynamics code for molten salt reactors
publisher Elsevier
series Nuclear Engineering and Technology
issn 1738-5733
publishDate 2021-02-01
description The Molten Salt Reactor (MSR), one of the six advanced reactor types of the 4th generation nuclear energy systems, has many impressive features including economic advantages, inherent safety and nuclear non-proliferation. This paper introduces a system analysis code named TREND, which is developed and used for the steady and transient simulation of MSRs. The TREND code calculates the distributions of pressure, velocity and temperature of single-phase flows by solving the conservation equations of mass, momentum and energy, along with a fluid state equation. Heat structures coupled with the fluid dynamics model is sufficient to meet the demands of modeling MSR system-level thermal-hydraulics. The core power is based on the point reactor neutron kinetics model calculated by the typical Runge-Kutta method. An incremental PID controller is inserted to adjust the operation behaviors. The verification and validation of the TREND code have been carried out in two aspects: detailed code-to-code comparison with established thermal-hydraulic system codes such as RELAP5, and validation with the experimental data from MSRE and the CIET facility (the University of California, Berkeley’s Compact Integral Effects Test facility).The results indicate that TREND can be used in analyzing the transient behaviors of MSRs and will be improved by validating with more experimental results with the support of SINAP.
topic Molten salt reactor
Transient analysis
Code development
Verification and validation
url http://www.sciencedirect.com/science/article/pii/S1738573319308046
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