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Perspective from Japan in the area of proven technology
Masaomi KOYAMADeputy Director
Nuclear Energy Policy Planning DivisionMinistry of Economy, Trade and Industry
INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria
New Technology and Proven Technology?
INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria
A lot of new comers expect vendors to use both the NEW / INNOVATIVE / ADVANCED and PROVEN technology for new nuclear power plants.
A lot of new comers expect vendors to use both the NEW / INNOVATIVE / ADVANCED and PROVEN technology for new nuclear power plants.
“NEW”
and “PROVEN”? “NEW”
but “PROVEN”?
‐
Does the new technology consist with proven technology?
‐
What is the “Proven Technology”?
‐
What is the proven technology on new technology?
‐
Is proven technology contradicted new technology?
1
“proven technology” requires proof of elemental technology and also proof of a plant total system.
The proof of elemental technology can be established by proof tests.
How “prove” a certain new/innovative/advanced technology for nuclear power generating system?
The proof of a plant total system must wait until construction and operation over a certain period of at least one or two lead plants.
Definition of “new technology” requires innovations of plant total performance that can differentiate the conventional plants. In most cases new elemental technology brings the innovations. However, this is not limited to hardware.
INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria
Proving “New”
Technology?
2
APWR and ABWR are the most advanced and have operated or constructed nuclear power system which have been used “proven technologies”.
How prove or how implement new technologies to the nuclear power generating system?
INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria
Tokyo Electric Power Co.Kashiwazaki-Kariwa NPS No. 6, 7
(In Operation)
Japan Atomic Power Co.Tsuruga NPS No. 3, 4
(Under preparatory work)
1st ABWR in the world 1st APWR in the world
Development of Advanced LWR
(1)
3
・Technology transfer
LessonsLearned Phase-1
Improvement & Standardisation Programmmes in JAPAN
Improvement & Standardization of conventional reactors (BWR & PWR)- Reliability, Radiation, Maintenance
Phase-2
Phase -3
ABWRDevelopment of advanced reactors
(ABWR & APWR)
1960s 1970s 1980s 1990s 2000s
INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria
Pictures: Property of Hitachi-GE Nuclear Energy, Mitsubishi Heavy Industries
APWR
Development of Advanced LWR
(2)
4
Development of Advanced LWR
(3)Sharing experiences of Introduction and Operation of NPPs with
electricity utilities and plant manufacturers‐
Contribution to safety and stable operation on NPPs
The 3rd Project on Improvement and Standardization of Light Water Reactor (1981‐1985) = Development ABWR
and APWR
Underperformance of early BWR and PWR in Japan‐
SCC (BWR)
‐ Leakage from Steam Generator Tube (PWR)‐
Longer Periodical Inspection Length than expected etc.
Development Objectives = Users CriteriaDevelopment Objectives = Users Criteria
5
First time to make users criteria in the worldFirst time to make users criteria in the world
Drastic approach to implement proven technologyDrastic approach to implement proven technology
INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria
The 3rd Project on Improvement and Standardization of Light Water Reactor (1981‐1985)
Concept design, Basic design, R &D
Vendors
Concept design, Basic design, R &D
Vendors
Collaborate R & DElectric Power Companies
and Vendors
Collaborate R & DElectric Power Companies
and Vendors
INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria
Development of Advanced LWR
(4)
Confirmatory TestingMinistry of International Trade and Industry
andNuclear Power Engineering Corporation
Confirmatory TestingMinistry of International Trade and Industry
andNuclear Power Engineering Corporation
Third party evaluationThe committee of improvement and standardization of nuclear power generating system
6
Major Requirements by User (Electricity Utilities)-Further improvement of safety and reliability
CDF <1/10 of conventional one-Reduction of radioactive waste
Quantities of waste drum <1/8 of conventional one-Radiation dose exposure for workers
Below 1/3 to conventional one-Improvement economic efficiency
Unit construction cost: approx. 80% of conventional oneStandard periodic inspection duration: 45daysStandard construction period: 48months
*As above, the user requirements of this time were only designing and development
User‐requirement‐based development by plant manufacturers, electricity
utilities and government
Example: Advanced Boiling Water Reactor (ABWR)
Great success of ABWR:4 plants in operation and 3 plants under construction in the globe
7INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria
The ABWR is the only existing and operating GIII proven technology in the world.
Development of Advanced LWR
(ABWR)
(1)
Adoption of Proven Technologies1980 2000 2010 2020
ABWR
BWROperation Plant
Containment Vessel Seismic Verification
Retrofit
Adoption
New Pump Verification
Utility Requirement
Evaluation by Advisory Gr. (Government level)
Construction/Operation
First of a kind development by manufacturer
Utility acceptance
Verification Tests-New Pumps
-Seismic Tests-Safety Systems-Containment Vessel-Reactor Internals
etc.
1990
Photographs: Property of Hitachi-GE Nuclear Energy INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria
Development of Advanced LWR
(ABWR)
(2)
8
Reinforced concreteContainment Vessel(RCCV)
52inch long turbine blade Moisture SeparatorRe-heater(MSR)
Recirculation Internal Pump(RIP)
Improvement of Safety
Intelligent Man-machine Interface
Avoidance of large-size pipe breakingaccident by adopting RIP3-system multiplex ECCS
Improvement of OperationPrecise power control by FMCRD/RIPIntelligent Man-machine Interface
Improvement of EconomyImprovement of thermal efficiencyby 52inch turbine blade and MSR
Improvement of Reliability
Dual CR drive system(FMCRD)
Digital Instrument and Control SystemFine Motion Control Rod Drive
(FMCRD)
Downsizing building volume
Advanced Technologies ‐
Features of ABWR ‐
INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria
Property of Hitachi-GE Nuclear Energy
Development of Advanced LWR
(ABWR)
(3)
9
70’s 80’s 90’s 2000’s 2010’s 2020’s
Enhanced up to APWR
APWR Tsuruga-3/4licensing process
Improvement & Development of PWR Technology
US-APWRUS NRC Licensing
US Utilities
CustomizingFor European Utilities EU-APWR
European Utilities
INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria
Development of Advanced LWR
(APWR)
(1)
10
Verifications for New Designs
1995 2000 2005
Performance, Flow, Seismic Tests
Performance and Flow Tests
Performance Tests
Licensing of Tsuruga #3/4
• Reactor Internals and Neutron Reflector Flow Tests
Operability Tests with Simulator
Performance and Vibration Tests
Reactor Flow Test
Separator Test
RCP Test
LP Turbine Test
• Compact SG and Improved Separator
• Safety System and Advanced Accumulator
• High-performance RCP
• Advanced I&C System
• Main Steam Turbine
INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria
Photographs: Property of Mitsubishi Heavy Industries
Development of Advanced LWR
(APWR)
(2)
11
Design tool ・3-Dimensional CADSystem design ・Advanced Accumulator in ECCS
・Advanced I & C System with FullDigital Safety Protection System
・Advanced Operator Console Board・Full 4 Trains of Safety System・Top Mounted ICIS
Components ・Reactor Internals with Neutron Reflector・Improved Steam Separator of SG・High Performance Reactor Coolant Pump・High Performance Steam Turbine・14-ft Fuel Assembly with AdditionalThermal Margin
Fabrication ・Laser Beam WeldingInspection tool ・Arrayed UT Machine
Example of innovative technologies for APWR
INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria
Development of Advanced LWR
(APWR)
(3)
12
The World Largest Class 1,700MWe Generated by “Our Own” Technologies
NSSS Thermal Output 4,466MWt
Enhanced SG Heat Transfer Area (8,500m2/unit) with Triangular Lattice of SG Tubes,
High-Performance Steam-Water Separators Generate High Quality Steam,
High Performance LP-Turbine System with last end Blade of 70 inches class.
High thermal efficiency over 36%
INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria
Figures: Property of Mitsubishi Heavy Industries
Progressing:
US/EU‐APWR 1700MWe Gen‐III+PWR
(1)
Development of Advanced LWR
(APWR)
(4)
13
Safe, Reliable and Economical Plant
Top Mounted ICIS for avoiding Penetrations at the RV Bottom,
Full 4-Train Safety Systems with Best Mix of Passive and Active Systems, Allowing On-Line Maintenance (OLM),
14-ft Fuels Creating Additional Thermal Margin and Making 24-Month Extended Cycle Operation without Deterioration in Fuel Economy,
Full Digital I&C Technology enabling one man operation.
SH SH
SHSH
RWSP
RVACC ACC
INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria
Pictures: Property of Mitsubishi Heavy Industries
Development of Advanced LWR
(APWR)
(5)Progressing:
US/EU‐APWR 1700MWe Gen‐III+PWR
(2)
14
“NEW” but “PROVEN” technology consists ofa) proof of elemental technology by proof test programmes and evaluation and authorization by authorities.b) innovative plant total performance that can differentiates the conventional plants.c) proof of an actual plant by construction and operation over a certain period of at least 1 or 2 lead plants.
These three key items certify the desirable nuclear innovations for technology users, that is “new and proven technology” for users.
Lessons
Learned
From
Development of LWRs
INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria 15
How do we check that nuclear power generating system is composed by proven technologies?
Suggestions for Users to introduce a newly designed plant
(1)
‐
It is not realistic that user countries check the maturity of the each technical elements because
very much manpower will be needed.‐
It is recommended that you evaluate
comprehensively the whole system of nuclear power plants.
INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria 16
Suggestions for Users to introduce a newly designed plant
(2)
Confirm the three key items that define the “new and proven technology.”
– a) proof of elemental technology
by proof test programmes and evaluation and authorisation by
authorities.– b) innovative plant total performance
that can
differentiates the conventional plants.– c) proof of an actual plant by construction and
operation
over a certain period of at least 1 or 2 lead plants.
Select a newly designed plant that has at least 1 or 2 lead operating plants. Otherwise, technology users will be
burdened undue risk of plant development that technology holders must owe.
INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria 17
‐
To implement the audit or inspection needs a considerable number of expert engineers. It is not
realistic to build up all of them in a user state.
‐
A realistic and easiest way is to entrust the tasks to neutral commercial service.
Suggestions for Users to introduce a newly designed plant
(3)
INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria 18