Operation characteristic of Integrated Pressurized Water Reactor under coordination control scheme

被引:16
作者
Du, Xue [1 ]
Xia, Genglei [2 ]
He, Lihui [3 ]
机构
[1] Harbin Engn Univ, Coll Automat, Harbin, Peoples R China
[2] Harbin Engn Univ, Fundamental Sci Nucl Safety & Simulat Technol Lab, Harbin, Peoples R China
[3] Harbin Normal Univ, Coll Comp Sci & Informat Technol, Harbin, Peoples R China
关键词
OTSG; Coordination control scheme; RELAP5; code; Operation boundary; VERTICAL ANNULAR CHANNEL; HEATED TURBULENT UPFLOW; SAFETY FEATURES; DESIGN; FLOW;
D O I
10.1016/j.anucene.2014.08.066
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Once-Through Steam Generator (OTSG) with smaller size and larger heat transfer capability, is typically used for Small and Medium sized Reactors (SMRs). Because the Integrated Pressurized Water Reactor (IPWR) uses OTSG, the feed water is heated to superheated steam by primary coolant, and the higher steam temperature could improve the thermal efficiency of the reactor power plant. However, the smaller size and heat capacity make stable operation more difficult. In this paper, a mathematical model of IPWR is established using RELAP5 code, and a coordination control scheme is used to study the rapid load following characteristics of OTSG. The effects of main operating parameters related to stable operation of OTSG are investigated. Average coolant temperature, steam pressure and OTSG grouping run operation boundary are confirmed. This operation boundary can be used to design and optimize the control system. (C) 2014 Elsevier Ltd. All rights reserved.
引用
收藏
页码:658 / 664
页数:7
相关论文
共 17 条
[1]   Safety evaluation of the inherent and passive safety features of the smart design [J].
Bae, KH ;
Kim, HC ;
Chang, MH ;
Sim, SK .
ANNALS OF NUCLEAR ENERGY, 2001, 28 (04) :333-349
[2]   The design and safety features of the IRIS reactor [J].
Carelli, MD ;
Conway, LE ;
Oriani, L ;
Petrovic, B ;
Lombardi, C ;
Ricotti, ME ;
Barroso, ACO ;
Collado, JM ;
Cinotti, L ;
Todreas, NE ;
Grgic, D ;
Moraes, MM ;
Boroughs, RD ;
Ninokata, H ;
Ingersoll, DT ;
Oriolo, F .
NUCLEAR ENGINEERING AND DESIGN, 2004, 230 (1-3) :151-167
[3]   Advanced operational strategy for the IRIS reactor: Load follow through mechanical shim (MSHIM) [J].
Franceschini, Fausto ;
Petrovic, Bojan .
NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (12) :3240-3252
[4]   CAREM project:innovative small PWR [J].
Fukami, MVI ;
Santecchia, A .
PROGRESS IN NUCLEAR ENERGY, 2000, 37 (1-4) :265-270
[5]   Integrated modular water reactor (IMR) design [J].
Hibi, K ;
Ono, H ;
Kanagawa, T .
NUCLEAR ENGINEERING AND DESIGN, 2004, 230 (1-3) :253-266
[6]   Coordination control and simulation for small nuclear power plant [J].
Hu Ping ;
Zhao Fuyu ;
Tai Yun .
PROGRESS IN NUCLEAR ENERGY, 2012, 58 :21-26
[7]  
INEL, 1998, NUREGCR5535 USNRC
[8]  
Kang H. O., 2008, P 16 INT C NUCL ENG
[9]   Isothermal and heated turbulent upflow in a vertical annular channel - Part I. Experimental measurements [J].
Kang, S ;
Patil, B ;
Zarate, JA ;
Roy, RP .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2001, 44 (06) :1171-1184
[10]   Neutronics and thermal hydraulic coupling analysis of integrated pressurized water reactor [J].
Khan, Salah Ud-Din ;
Peng, Minjun ;
Khan, Shahab Ud-Din .
INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2013, 37 (13) :1709-1717