ACP600

General Descriptions

ACP600 is a medium-sized advanced pressurzed water reactor product independently developed by CNNC . Based on mature nuclear power technology of CP600, it takes reference of the design philosophy of the advanced PWRs around the globe, adopts the ‘Active + Passive’ safety design technology and is able to meet utility requirements for Gen III NPP.

Proven
Normal operation system based on mature technology with rich operation experiences and excellent performances Proven equipments and manufacturing capability Mature design tools and data base Evolutionary technical improvements verified and evaluated by a series of experiments and tests
Safe
Active + passive design philosophy Increased safety margin Digital IC and advanced MCR Improved configurations of engineering safety features Complete SA prevention & mitigation measures Reinforced protection against external hazards Improved emergency response capability
Economic
Extended refueling cycle of 18 months High plant availability ≥ 90% Prolonged plant design lifetime of 60 years Construction period and cost under control Mature equipment procurement channel Advanced technology like integrated head assembly , LBB reducing refueling /maintenance cost

IMPORTANT PARAMENTERS

No.	Design Description	Unit	Parameters
1	Nominal Electric Power	MWe	≥670
2	Designed Lifetime	Year	60
3	Refueling Cycle	Month	18(with capability to extend to 24 months)
4	Plant Availability	%	≥90
5	Peak Ground Acceleration	g	0.3
6	Core Damage Frequency	1/reactor year	＜1×10^-6
7	Large Release Frequency	1/reactor year	＜1×10^-7
8	Occupational Exposure Dose	m Sv/reactor year	＜0.5
9	Operator Nonintervention Period	Minute	＞30
10	Plant Autonomy Period	Hour	72

PLANT LAYOUT

Single-unit Layout

DOUBLE-SHELL CONTAINMENT

Double-Shell Containment

Inner shell

Inner shell

Prestressed reinforced concrete with a leak-tight steel liner inside High tensile strength
Outer shell

Outer shell

Reinforced concrete Withstanding large commercial aircraft crash
Annular space

Annular space

Keeping negative pressure Collection and filtration of the leak

SAFETY FEATURES

Beyond-Design-Base-Accident(BDBA)/Severe Accident(SA) Prevention and Mitigation

Phenomena		Containment failure
Containment failure	Hydrogen Detonation	Containment Hydrogen Combination System
	High Pressure Molten Corium Ejection, Direct Containment Heating, Induced SGTR	Fast Depressurization System for RCS
	Long Term Overpressure	Containment Filtration and Venting System Passive Containment Heat Removal System
	Basement Melt-through	Reactor Cavity Injection and Cooling System
	Station Blackout	Passive Residual Heat Removal System of Secondary Side
	Other Measure	RPV High-point Venting System, Habitability Design of Main Control Room, SAMG and etc.

Feedbacks from Fukushima Accident

Protection against External Events

Double-shell containment Seismic design with input of 0.3g peak ground acceleration Protection against large commercial air crash

General Descriptions Important Paramenters Plant Layout Double-Shell Containment Safety Features

ACP600

Active & Passive Medium-sized Advanced PWR

General Descriptions

Proven

Safe

Economic