ACPR1000 +

1. The Third Generation Nuclear Reactor ACPR1000+ Advanced, cost competitive, proven technology, and reliable

2. Content I. Summary II. Main Features III. Key Figures of Comparative Reactors IV. Roadmap V. Technology Introduction VI. Regulator Evaluation

3. 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.

4. 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

5. 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

6. 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. 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. III. Key Figures of Comparative Reactors

10. 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

11. 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.

12. 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.

13. 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

14. 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. CPR1000 ACPR1000+

15. 7. Site Adaptability • Improved SSE • 0.2g→ 0.3g • Single reactor layout • Physical separation pattern, to improve safety • Flexible to the grid

16. 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

17. 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.

18. 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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