Dynamic Modeling and Control Characteristics of the Two-Modular HTR-PM Nuclear Plant

The modular high temperature gas-cooled reactor (MHTGR) is a typical small modular reactor (SMR) with inherent safety feature. Due to its high reactor outlet coolant temperature, the MHTGR can be applied not only for electricity production but also as a heat source for industrial complexes. Through...

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Main Authors: Zhe Dong, Yifei Pan, Maoxuan Song, Xiaojing Huang, Yujie Dong, Zuoyi Zhang
Format: Article
Language:English
Published: Hindawi Limited 2017-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2017/6298037
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spelling doaj-b62d7afbc1154c149256d9858c24b2cf2020-11-24T21:06:09ZengHindawi LimitedScience and Technology of Nuclear Installations1687-60751687-60832017-01-01201710.1155/2017/62980376298037Dynamic Modeling and Control Characteristics of the Two-Modular HTR-PM Nuclear PlantZhe Dong0Yifei Pan1Maoxuan Song2Xiaojing Huang3Yujie Dong4Zuoyi Zhang5Institute of Nuclear and New Energy Technology, Collaborative Innovation Centre of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Collaborative Innovation Centre of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Collaborative Innovation Centre of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Collaborative Innovation Centre of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Collaborative Innovation Centre of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, ChinaInstitute of Nuclear and New Energy Technology, Collaborative Innovation Centre of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing 100084, ChinaThe modular high temperature gas-cooled reactor (MHTGR) is a typical small modular reactor (SMR) with inherent safety feature. Due to its high reactor outlet coolant temperature, the MHTGR can be applied not only for electricity production but also as a heat source for industrial complexes. Through multimodular scheme, that is, the superheated steam flows produced by multiple MHTGR-based nuclear supplying system (NSSS) modules combined together to drive a common thermal load, the inherent safety feature of MHTGR is applicable to large-scale nuclear plants at any desired power ratings. Since the plant power control technique of traditional single-modular nuclear plants cannot be directly applied to the multimodular plants, it is necessary to develop the power control method of multimodular plants, where dynamical modeling, control design, and performance verification are three main aspects of developing plant control method. In this paper, the study in the power control for two-modular HTR-PM plant is summarized, and the verification results based on numerical simulation are given. The simulation results in the cases of plant power step and ramp show that the plant control characteristics are satisfactory.http://dx.doi.org/10.1155/2017/6298037
collection DOAJ
language English
format Article
sources DOAJ
author Zhe Dong
Yifei Pan
Maoxuan Song
Xiaojing Huang
Yujie Dong
Zuoyi Zhang
spellingShingle Zhe Dong
Yifei Pan
Maoxuan Song
Xiaojing Huang
Yujie Dong
Zuoyi Zhang
Dynamic Modeling and Control Characteristics of the Two-Modular HTR-PM Nuclear Plant
Science and Technology of Nuclear Installations
author_facet Zhe Dong
Yifei Pan
Maoxuan Song
Xiaojing Huang
Yujie Dong
Zuoyi Zhang
author_sort Zhe Dong
title Dynamic Modeling and Control Characteristics of the Two-Modular HTR-PM Nuclear Plant
title_short Dynamic Modeling and Control Characteristics of the Two-Modular HTR-PM Nuclear Plant
title_full Dynamic Modeling and Control Characteristics of the Two-Modular HTR-PM Nuclear Plant
title_fullStr Dynamic Modeling and Control Characteristics of the Two-Modular HTR-PM Nuclear Plant
title_full_unstemmed Dynamic Modeling and Control Characteristics of the Two-Modular HTR-PM Nuclear Plant
title_sort dynamic modeling and control characteristics of the two-modular htr-pm nuclear plant
publisher Hindawi Limited
series Science and Technology of Nuclear Installations
issn 1687-6075
1687-6083
publishDate 2017-01-01
description The modular high temperature gas-cooled reactor (MHTGR) is a typical small modular reactor (SMR) with inherent safety feature. Due to its high reactor outlet coolant temperature, the MHTGR can be applied not only for electricity production but also as a heat source for industrial complexes. Through multimodular scheme, that is, the superheated steam flows produced by multiple MHTGR-based nuclear supplying system (NSSS) modules combined together to drive a common thermal load, the inherent safety feature of MHTGR is applicable to large-scale nuclear plants at any desired power ratings. Since the plant power control technique of traditional single-modular nuclear plants cannot be directly applied to the multimodular plants, it is necessary to develop the power control method of multimodular plants, where dynamical modeling, control design, and performance verification are three main aspects of developing plant control method. In this paper, the study in the power control for two-modular HTR-PM plant is summarized, and the verification results based on numerical simulation are given. The simulation results in the cases of plant power step and ramp show that the plant control characteristics are satisfactory.
url http://dx.doi.org/10.1155/2017/6298037
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