Combined Heat and Power Design Considerations for the APR1400  

作　　者：Michal Wierzchowski Robert M. Field 

机构地区：[1]KEPCO International Nuclear Graduate School (KINGS), 658-91 Haemaji-ro, Seosaeng-myeon, Ulju-gun, Ulsan 689-882, Republic of Korea

出　　处：《Journal of Energy and Power Engineering》2017年第3期195-203,共9页能源与动力工程（美国大卫英文）

摘　　要：To date, nuclear cogeneration applications have been limited, primarily to district heating in Eastern Europe and heavy water production in Canada. With the current global price for oil and energy, this technology is not economically viable for most countries. However, oil and fossil fuel prices are known to be highly volatile, and the Paris Agreement calls for a reduction in fossil fuel use. Under these circumstances, heat supplied by nuclear power may abruptly return to favor. To prepare for such a scenario, this study will investigate design considerations for a prototypical modem nuclear power plant, the Korean APR1400 （advanced power reactor 1400） （e.g., Shin Kori Units 3, 4, Shin Hanul 1, 2, Barakah Units 1, 2, 3, 4）. Nuclear cogeneration can impact balance of plant system and component design for the condensate, feedwater, extraction steam, and heater drain systems. The APR1400 turbine cycle will be reviewed for a parametric range of pressures and flow rates of the steam exported for cogeneration to identify major design challenges.

关 键 词：COGENERATION ENERGY HEAT nuclear energy steam turbine DESIGN pressurized water reactor APR1400. 

分 类 号：TM623.1[电气工程—电力系统及自动化] TM621