Transcript The Third Generation Nuclear Reactor ACPR1000+

The Third Generation Nuclear Reactor
ACPR1000+
Advanced, cost competitive, proven technology, and reliable
1
Content
I. Summary
II. Main Features
III. Key Figures of Comparative Reactors
IV. Roadmap
V. Technology Introduction
VI. Regulator Evaluation
2页
I. Summary
– 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.
3页
II. Main Features
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
4页
2. Mature
Primary 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+
EPR
5页
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
6页
4. Economic
– 60 years of design lifetime
– Metal reflector to reduce fast neutron
flux 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.
7页
III. Key Figures of Comparative Reactors
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
8.1×10-8
＜1×10-6
ITEM
≤5.9×10-8
Electrical
Output， MWe
1150
1085
1250
1700
Improved
PWR upper
limit 1350
Core Thermal
Margin
>15%
10％
>15％
>15％
>15％
Fuel Cycle ，
month
18-24
18
18
18
24
8页
ACPR1000+
CPR1000+
AP1000
EPR
URD/EUR
Capacity
Factor，%
92
≥90
93
≥92
87
SSE，g
0.3
0.2
0.3
0.25
EUR 0.25
URD 0.3
30min
10min
72hour
30min
At least
30min
＜50
<50
<50
>50
60
60
60
60
ITEM
Period without
operator actions
Solid waste
generation，
m3/(a·Unit)
Design lifetime,
Year
60
9页
IV. Technology Introduction
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,
structure simplified, RPV design lifetime prolonged
10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.
Accident mitigation capacity is
enhanced.
11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.
12页
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
13页
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
CPR1000
design basis accident is improved.
•
The double containment further reduces
the radioactive release to environment
during severe accident.
ACPR1000+
14页
7. Site Adaptability
– Improved SSE
• 0.2g→ 0.3g
– Single reactor layout
• Physical separation pattern, to improve safety
• Flexible to the grid
15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
© AREVA
– Emergency response plan
Scheme of the Passive Autocatalytic Recombiner –
Totally passive technology
16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.
17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)
18页
Thanks!
19页