•Forced natural circulation between reactor core and steam generator •Emergency heat exchanger submerged in the cooling pool •Passive decay heat removal system provides cooling for 3 days without operator intervention or 14 days with water supply from cooling pool by gravity
•Core cooling using natural circulation between steel shell and reactor core •Passive core cooling provides cooling for 3 days without operator intervention or 14 days with water supply from cooling pool by gravity
• Flexible configuration with 1~8 modules • 30 months construction time • Smaller construction area • Smaller emergency off-site area
• Easily transportable • 24 months fuel cycle or longer
• Designed lifetime for 60 years • Availability >90%
ACP100 is estimated to be competitive against large reactors if more than 4 modules are built simultaneously
Electricity & Heating
Electricity & water
Electricity & water
Electricity & Steam
High Temperature Gas Cooled Reactor -an effort towards Generation IV
HTR-PM
•
100Mwe per module
•
Inherent safety
•
Self contained TRISO Fuel
•
No off-site emergency area needed
•
High efficiency
•
No nuclear proliferation
•
Continuously refueling
•
Simplified system
•
Modular design
In 2004, HTR-10 has been proved to be able to stay within designed fuel element temperature when the coolant(helium) is removed, an extreme case of LOCA. LWR 100MW/m3
Maximum Fuel Temperature(ºC)
Fuel temperature limit
HTGR 3MW/m3
Low power density
Time(hour)
Negative reactivity to temperature In addition to the role of moderator, graphite also serve as a huge heat capacitor in HTGR
Heat radiation and cooling walls
Higher Efficiency
Helium circulator with electromagnetic bearing and helium turbine
Fuel post-process
Multiple Purpose
The generation cost is yet to be competitive comparing to large reactors Thermal power
500 Mw
Electric power
200 Mw
Modules
2
Core diameter
3 meters
Core height
11 meters
Helium pressure
7Mpa
Core exit temperature
750ºC
Core enter temperature
250ºC
Main steam temperature
566ºC
Steam pressure
13.25Mpa
2003 HTR-10 Full power
2009 HTR-PM ready for FCD
2011 Approved by government
Steam generator forgings
Construction Site
Reactor vessel forgings
•The need to reduce coal consumption is more urgent than ever •SMR could be an excellent substitution for coal in many situations in China •Despite of the achievement, a “lift off” is unlikely until the design is proven and regulation for SMR is perfected.
“China will……continue effectively develop nuclear power on the basis that safety is ensured.”
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