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Perspective from Japan in the area of proven technology Masaomi KOYAMA Deputy Director Nuclear Energy Policy Planning Division Ministry of Economy, Trade and Industry INPRO Dialogue Forum on Nuclear Energy Innovations 1-4 February 2010, IAEA Headquarters, Vienna, Austria

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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

Thank you for your attention!

INPRO Dialogue Forum on Nuclear Energy Innovations1-4 February 2010, IAEA Headquarters, Vienna, Austria