My name is Yong Soo Kim. I have responsibility for the development of Advanced Nuclear Power

Transcription

1 [slide 1] Good afternoon, ladies and gentlemen. My name is Yong Soo Kim. I have responsibility for the development of Advanced Nuclear Power Rectors for Europe, particularly Czech Republic. I wish that my presentation will contribute to improving your understandings regarding Korean Advanced Nuclear Power Rectors. [slide 2] As you can see in this slide, at first, I will introduce the history and the plan of Nuclear power reactor developments and construction in brief. And then, my presentation will be focused on EU-APR and APR1000, which are suggested designs for Czech new-build projects last year. [slide 3] Let s see the history and the plan for Nuclear power reactor development and construction. [slide 4] We have constructed Nuclear Power Plants after introducing the first unit, Kori 1, in As of May 2017, we, KHNP, are operating 25 units and constructing 7 units in Korea and 4 units in UAE. In addition to NPPs construction, we have developed continually advanced reactors such as APR1400, APR+, and I-Power and performed the customizing engineering of APR1400 to fit with the up-to-date nuclear requirements in Europe and US. Through design certification projects, their licensibilities have been verified in Europe and US.

2 [slide 5] This slide shows KHNP s strategy for Advanced Nuclear Reactor developments. According to the short-term strategy, we developed APR1400 and APR+ as an evolutionary concept of conventional nuclear reactor design and performed the customizing engineering projects for EU-APR, APR1000, and US-APR1400 to comply with market demands in respect of capacity and regulation in Europe and US. As a long-term strategy, we, KHNP, are developing I-power to improve NPP s safety innovatively in the revolutionary manner such as adoption of full passive safety systems. [slide 6] From now on, let s see how we, KHNP, developed and verified EU-APR. [slide 7] The reference design of EU-APR is APR1400, which was developed to fully comply with US ALWR regulations and EPRI utility requirements. As of May 2017, we, KHNP, are operating the first APR1400 commercial plant, Shin Kori unit 3, and constructing 7 units in Korea and 4 units in UAE, respectively. The EU-APR is the customized design of APR1400 for Europe incorporating the up-to-date nuclear requirements of EUR Rev. D, IAEA SSR-2/1, and WENRA as well as recommendations of EU stress test against Fukushima accident. [slide 8] The table show the major differences of EU-APR from other APR1400 series designs. Different from other APR1400 designs adopting US codes & standards, The EU-APR incorporates the nuclear requirements of IAEA, WENRA, and EUR and the European codes & standard such as SI unit, ASME and EN for mechanical design, IEC for electrical and I&C design, and IAEA GS-R-3

3 for QA. In addition, compared with other APR1400 designs, the EU-APR design was reinforced mainly in the respect of safety systems redundant and diverse design, external man-made hazard protection design, Severe Accidents mitigation systems from to satisfy more stringent acceptance criteria. In case of Large Break LOCA, the acceptance criterion of the EU-APR is 5 msv while other APR1400 designs apply 250 msv/2 hrs. [slide 9] The EU-APR licensaibility in Europe was verified through European Utility Requirements(EUR) certification assessment. We, KHNP, applied the EUR assessment at the end of The detailed assessment was successfully finished early this May and the EUR certification for the EU-APR will be issued this November. [slide 10] Now, let s move on to APR1000 design. [slide 11] The reference design of APR1000 is OPR1000, which was developed by combining two CE designs of ANO and Palo Verde NPPs. The first unit s commercial operation was started in 1995 and now 12 units are operated in Korea. The APR1000 is the customized design of OPR1000 complying with European codes and standard and the Advanced Design Features of EU-APR and APR+ were adopted into the APR1000 to satisfy the European up-to-date nuclear requirements.

4 [slide 12] The table show the major differences of APR1000 from the OPR1000 design. The EU-APR incorporates the nuclear requirements of IAEA, WENRA, and EUR and the European codes & standard such as SI unit, ASME and EN for mechanical design, IEC for electrical and I&C design, and IAEA GS-R-3 for QA. In addition, different from OPR1000, the APR1000 design adopted redundant and diverse safety systems, passive auxiliary fed-water system, external man-made hazard protection design, Severe Accidents mitigation systems from to satisfy more stringent acceptance criteria, 5 msv for the APR1000 and 250 msv/2 hrs for OPR1000 In case of Large Break LOCA. [slide 13] From now, I will introduce the major advanced design features of EU-APR and APR1000 one by one. [slide 14] Against external natural and man-made hazards, secondary containment is adopted and structural reinforced or physical separated design is applied to safety buildings, which house safety components such as RCS, Engineering Safety Features, and Emergency Diesel Generators. And, in order to monitor discharged gas and to enhance dispersion of discharged gas, 100 m height stack was installed. [slide 15] The safety systems mitigating DBC 3 & 4 accidents were designed N+2 considering single failure and 1 train on-power maintenance during the accident and the safety systems mitigating DBC 2, DEC and Severe accidents are designed N+1 considering single failure maintenance during the accident. The redundant design of safety systems contribute to reduce shutdown risk and to enhance the plant availability by reducing overhaul duration. As a diverse design of safety function, system or component level alternative measures are

5 equipped against common Cause Failures of safety systems in the event of DBC 2 & 3. [slide 16] In order to minimize the release of radioactive materials through securing the containment integrity during Severe Accidents, Severe Accidents dedicated mitigation systems such as Passive Corium Cooling system to prevent molten corium and concrete interaction, Emergency Reactor Depressurization System to prevent High Pressure Molten Ejection, and Passive Hydrogen Control system, and etc. are installed independent of safety systems for Design Basis Conditions. [slide 17] In addition to Advanced Design features mentioned in the previous slides, which are equipped in the EU-APR and the APR1000, the APR1000 adopts another Advanced Design feature of Passive Auxiliary Feed-water system replacing the active system in the conventional NPPs. The Passive Auxiliary Feed-water system improve the plant safety through core residual heat removal by natural circulation during the accidents. Particularly, in the extremely rare events such as Fukushima accident, the Passive Auxiliary Feedwater system can remove core residual heat for at least 72 hours without replenishment of external water and supply of external power. [slide 18] Considering extremely rare events such as Fukushima accident, the protection design against external flooding such as Elevated Site Height or waterproof doors can be incorporated. And, external cooling water injection paths into RCS, SG, and Spent Fuel Pool as well as mobile generator are installed against total loss of electrical power & ultimate heat sink. [slide 19]

6 I heard that Czech Nuclear Industry has the question for Whether EU-APR & APR1000 are proven designs or not. From now on, let s resolve your question. [slide 20] I would like to explain why EU-APR and APR1000 are proven designs based on the IAEA s definition for Proven Technology. [slide 21] In the IAEA document, NP-T-2.1, Section shown in the previous slide, the provenness of overall nuclear power plant systems should be demonstrated through several years operation of similar nuclear power plants as a commercial plant with a good operational record. The EU-APR reference plant, Shin-Kori uint 3, is operated with high performance without any transient after entering commercial operation on Feb Meanwhile, the APR1000 reference plant is Shin-wolsung unit 2, which has been operated without any operation problem after starting commercial operation on Jul In addition, all OPR1000 plants are operated with greater than 85% of availability. Thus, overall system performances of EU-APR and APR1000 are demonstrated through operation of similar plants. [slide 22] Besides, the IAEA document, NP-T-2.1, Section requires that the provenness of the elements should be demonstrated through several years of operation in existing NPP or fossil/process industries, or full or part scale test facilities. [slide 23] The modified designs of safety injection system adopted in the EU-APR and APR1000 were

7 verified through separate effect test such as Emergency Cooling water bypass test for the design of DVI with EBCD, Full scale coolant injection behavior for SIT with Fluidic Device, ECC strainer performance test. In addition, overall performance of safety injection system were demonstrated through integral loop test. [slide 24] The performance of Core Catcher, representative Severe Accidents Mitigation System was verified through corium-concrete interaction test and full scale natural cooling test for segmented cooling channel. [slide 25] The performance of Passive Auxiliary Feed-water system was demonstrated through full scale natural cooling test for single Heat Exchanger bundle. [slide 26] From now, let me summarize my presentation. [slide 27] As I showed you according to the IAEA definition for proven technology, the EU-APR and APR1000 are proven designs to satisfy the demands of Czech Nuclear Industry regarding capacity and regulations. KHNP can fulfill on-time and on-budget construction and delivery based on the accumulated technologies and know-how through continuous construction and operation of NPPs from Technical support will be provided for the customers through developing advanced technologies to enhance the plant performance. Czech Nuclear Industry is the best partner of KHNP to economically deploy Korean nuclear power plant in Europe using Czech industry infrastructure and competent human resource.

8 [slide 28] The end.