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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

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II. Main FeaturesII. Main Features

IV. RoadmapIV. Roadmap

VI. Regulator EvaluationVI. Regulator Evaluation

ContentContent

V. Technology IntroductionV. Technology Introduction

I. SummaryI. Summary

III. Key Figures of Comparative ReactorsIII. Key Figures of Comparative Reactors

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– 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. SummaryI. Summary

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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 FeaturesII. Main Features

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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

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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.

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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 ReactorsIII. Key Figures of Comparative Reactors

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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 actions30min 10min 72hour 30min At least

30min

Solid waste

generation ， m3/

(a·Unit)

＜ 50 <50 <50 >50

Design lifetime,Year

60 60 60 60 60

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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

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 IntroductionIV. Technology Introduction

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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.

Design basis is improved. Design basis is improved. Accident mitigation capacity is Accident mitigation capacity is enhanced.enhanced.

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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++

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7. Site Adaptability

– Improved SSE

• 0.2g→ 0.3g

– Single reactor layout

• Physical separation pattern, to improve safety

• Flexible to the grid

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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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RE

VA

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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.Meet the emission limits of inland plants.Meet the emission limits of inland plants.

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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)

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