Dynamic thermal performance analysis for fin-concrete ceiling in main control rooms of passive nuclear power plants

被引:5
作者
Huang, Yixiang [1 ]
Su, Xing [1 ]
Wu, Xiaoyan [1 ,2 ]
Ye, Wei [1 ,3 ]
Zhang, Xu [1 ]
机构
[1] Tongji Univ, Sch Mech Engn, Shanghai 200092, Peoples R China
[2] Jiaxing Univ, Coll Civil Engn & Architecture, Jiaxing 314001, Peoples R China
[3] Tongji Univ, Minist Educ, Key Lab Performance Evolut & Control Engn Struct, Shanghai 200092, Peoples R China
基金
中国国家自然科学基金;
关键词
Dynamic thermal performance; Passive cooling; Finned concrete; Thermal network model; COOLING SYSTEM; HEAT-PIPE; SIMULATION; INLEAKAGE; DESIGN; EXCHANGER;
D O I
10.1016/j.csite.2021.101402
中图分类号
O414.1 [热力学];
学科分类号
摘要
The main control rooms of passive nuclear plants must maintain a habitable environment once station-blackout accidents occur. In this condition, the heavy fin-concrete ceiling on the room will remove heat from kind of heat sources and protect from overheating environment. However, the dynamic thermal process of finned concrete ceiling has not been studied in various passive cooling measures. In this study, an efficient parametric resistance-capacitance thermal network model is established to describe dynamic thermal responses of heavy fin-concrete layer, and validated by dynamic temperature change data of a hot-box experiment for 24 h. Series indicators were deduced by analytic solutions. Based on the validated model and indicators, factor analysis was conducted to obtain details of effect of finned-plate geometric parameters and heat source intensity. The results show that initial 2-h thermal process can be divided into two stage, "transient stage" and "quasi-stable stage". The transient-stage thermal process is determined by source flux and finned coefficient of finned plate. The quasi-stable thermal process depends on thermal mass of the finned plate and heat source flux. Furthermore, there exists a linear relationship between air temperature and heat source flux. Finned plate layout can be design according to the factor assessment results.
引用
收藏
页数:16
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共 32 条
[1]   Design of condensation heat exchanger for the PAFS (Passive Auxiliary Feedwater System) of APR plus (Advanced Power Reactor Plus) [J].
Bae, Byoung-Uhn ;
Yun, Byong-Jo ;
Kim, Seok ;
Kang, Kyoung Ho .
ANNALS OF NUCLEAR ENERGY, 2012, 46 :134-143
[2]   Parametric analyses for the design of a closed-loop passive containment cooling system [J].
Bang, Jungjin ;
Hwang, Ji-Hwan ;
Kim, Han Gon ;
Jerng, Dong-Wook .
NUCLEAR ENGINEERING AND TECHNOLOGY, 2021, 53 (04) :1134-1145
[3]   Cold Concrete Envelopes with Fins Regulating Control Rooms Temperature under Accident Conditions [J].
Chang, Le ;
Zhang, Xu ;
Cai, Yingying .
10TH INTERNATIONAL SYMPOSIUM ON HEATING, VENTILATION AND AIR CONDITIONING, ISHVAC2017, 2017, 205 :3493-3496
[4]   Dynamic simulation of contaminant inleakage produced by human walking into control room [J].
Chang, Le ;
Tu, Shuyang ;
Ye, Wei ;
Zhang, Xu .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2017, 113 :1179-1188
[5]   Experimental determination of air inleakage to pressurized main control room caused by personnel entering [J].
Chang, Le ;
Zhang, Xu ;
Cai, Yingying .
BUILDING AND ENVIRONMENT, 2016, 99 :142-148
[6]   Control room contaminant inleakage produced by door opening and closing: Dynamic simulation and experiments [J].
Chang, Le ;
Zhang, Xu ;
Wang, Shengji ;
Gao, Jun .
BUILDING AND ENVIRONMENT, 2016, 98 :11-20
[7]   Design of integrated passive safety system (IPSS) for ultimate passive safety of nuclear power plants [J].
Chang, Soon Heung ;
Kim, Sang Ho ;
Choi, Jae Young .
NUCLEAR ENGINEERING AND DESIGN, 2013, 260 :104-120
[8]   Fork-end heat pipe for passive air cooling of spent nuclear fuel pool [J].
Choi, Jonghwi ;
Lim, Changhwan ;
Kim, Hyungdae .
NUCLEAR ENGINEERING AND DESIGN, 2021, 374 (374)
[9]   Conceptual benefits of passive nuclear power plants and their effect on component design [J].
DeVine, JC .
NUCLEAR ENGINEERING AND DESIGN, 1996, 165 (03) :299-305
[10]   Effect of condenser tube inclination on the flow dynamics and instabilities in a passive containment cooling system (PCCS) for nuclear safety [J].
Haag, Michel ;
Selvam, P. Karthick ;
Leyer, Stephan .
NUCLEAR ENGINEERING AND DESIGN, 2020, 367