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ACPR1000ACPR1000++
Advanced, cost competitive, proven technology, and reliableAdvanced, cost competitive, proven technology, and reliable
The Third Generation Nuclear ReactorThe Third Generation Nuclear Reactor
2页
II. Main Features
IV. Roadmap
VI. Regulator Evaluation
Content
V. Technology Introduction
I. Summary
III. Key Figures of Comparative Reactors
3页
– ACPR1000+ is an advanced nuclear power technology developed by CGNPC with independent intellectual property right.
– Main performances meet the technical standards of the third generation technology and the requirements of Post-Fukushima.
– Its engineering work is being made taking advantage of proven technology and experience feedback, in line with the national and international laws and regulations.
– Pursuing superb safety performance is focused, with due consideration to economic competitiveness, which satisfy the multiple requirements of the users in China and abroad.
I. Summary
4页
1. Advanced– Meet the safety requirements of post-Fukushima
– Meet the HAF102 and refer to relevant URD/EUR requirements
– Fully achieve the third generation targets
II. Main Features
5页
2. MaturePrimary system design, loop configuration and main equipment are similar to the PWR NPPs in operation. Experience feedback from design, construction and operation of PWR NPPs, including EPR, are taken into account. Validated and proven technologies are referred to for its design.
• Over 1,000 reactor years operating experience of the similar NPPs
• Complete and mature industry systems for primary equipment manufacturing
• Extensive construction experience
CPR1000+CPR1000+ EPREPRCPR1000CPR1000
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3. Safe
– Three independent trains of safety systems;
– Decreased linear power density to increase
core thermal margin;
– Double containment to protect against
airplane crash and external explosion;
– Improved seismic capability;
– Effective mitigation measures for severe
accidents
7页
4. Economic
– 60 years of design lifetime
– Metal reflector to reduce fast neutronflux in RPV
– Online maintenance
– 18-month fuel cycle
– Improved seismic capability to increase the site adaptability
– Centralized disposal of radioactive waste to improve volume reduction ratio.
8页
ITEM ACPR1000+ CPR1000+ AP1000 EPR URD/EUR
Core Damage Frequency ，/(pile·year)
＜ 1×10-5 ～ 1×10-5 ≤5.1×10-7 7.75×10-7 ＜ 1×10-5
Large Release Frequency ， /(pile·year)
＜ 1×10-6 ～ 1×10-6 ≤5.9×10-8 8.1×10-8 ＜ 1×10-6
Electrical Output ， MWe
1150 1085 1250 1700Improved
PWR upper limit 1350
Core Thermal Margin
>15% 10 ％ >15 ％ >15 ％ >15 ％Fuel Cycle ， month
18-24 18 18 18 24
III. Key Figures of Comparative Reactors
9页
ITEM ACPR1000+ CPR1000+ AP1000 EPR URD/EUR
Capacity Factor ， % 92 ≥90 93 ≥92 87
SSE ， g 0.3 0.2 0.3 0.25 EUR 0.25URD 0.3
Period without operator actions
30min 10min 72hour 30min At least30min
Solid waste generation ， m3/(a·Unit)
＜ 50 <50 <50 >50
Design lifetime,Year
60 60 60 60 60
10页
1. Reactor– 157 fuel assemblies (active length 14 feet)
• Core thermal power is increased by 10.5% and core average linear power density (LPD) is decreased by 5.5%, comparing to CPR1000+;
– In-core instrumentation inserted from the top;
– Metal reflector to extend the RPV design lifetime to 60 years.
Core safety margin and fuel burnup are increased,Core safety margin and fuel burnup are increased,structure simplified, RPV design lifetime prolonged structure simplified, RPV design lifetime prolonged
IV. Technology Introduction
11页
2. Nuclear Steam Supply System (NSSS)
– Heat transfer area of steam generator (SG) is increased by 28% compared with
CPR1000+ ；– Pressurizer cavity is increased by 26% compared with CPR1000+ ；– Large capacity pressure relief valve introduced to the pressure relief system for
reactor coolant system to quick relief coolant in severe accident conditions ；– LBB technology is adopted to simplify the system design.
Design basis is improved. Design basis is improved. Accident mitigation capacity is Accident mitigation capacity is enhanced.enhanced.
12页
3. NI Auxiliary System– Residual heat removal system is combined with low pressure safety injection
system;
– RCV (Chemical and Volume Control) is simplified, to execute non–safety related functions only;
– Two independent trains of spent fuel cooling systems are set up to improve the safety of spent fuel storage.
4. Engineered Safety Systems
– Three independent trains of safety systems are installed in physical
separation pattern, which are backup for each other,
– Simplified system design,
– In-containment water storage.
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5. Advanced I&C Systems– Optimized DCS system and state-of-the-art operator information system
– Sequence control technology, to improve automation and reduce the burden
of the operator
– DAS (Diversity Actuation System), to further improve safety and reliability
– Improved ventilation system, to improve the habitability of main control room
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6. Double Containments
• The outer containment can withstand
large commercial aircraft crash and
improve the safety.
• The cavity in containment is enlarged.
The emergency response ability to
design basis accident is improved.
• The double containment further reduces
the radioactive release to environment
during severe accident.
CPR1000CPR1000
ACPR1000ACPR1000++
15页
7. Site Adaptability
– Improved SSE
• 0.2g→ 0.3g
– Single reactor layout
• Physical separation pattern, to improve safety
• Flexible to the grid
16页
8. Severe Accident Mitigation Measures– High-pressure core melting, hydrogen explosion, RPV melt wear,
containment overpressure and heat discharge…
• Pressurizer pressure relief
• IVR (in-vessel retention)
• Passive autocatalytic recombiners and igniters
– SAMG
– Emergency response plan
Scheme of the Passive Autocatalytic Recombiner –Totally passive technology
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17页
9. Waste Management
– Centralized disposal of radioactive wastes from the pile
• Less buildings, to shorten the construction period of NI
• Minimized waste release, solid waste generation for a reactor is less than 50m3/a 。
– Advanced tritium removal technology
Meet the emission limits of inland plants.Meet the emission limits of inland plants.
18页
10. Tests– Integral scaling of hydraulic test for RPV
– CRDM drive line test
– Internals flow-induced vibration test
– IVR test (RPV bottom head cooling performance test)
19页
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