technology overview and gda update - horizon nuclear · pdf filetechnology overview and . gda...

© Hitachi, Ltd. 2012. All rights reserved. Commercial in Confidence

Shunsuke Utena General Manager

Europe Nuclear Energy Development Division Hitachi, Ltd.

Technology Overview and GDA Update

May 21st and 23rd, 2013

Horizon Supply Chain Events

Hitachi, Ltd. 2013. All rights reserved.




1. Technical feature of ABWR

Contents

2. Fukushima Lessons Learned 3. GDA Update 4. ABWR Introduction Video

5. Unique Construction Technologies

6. Conclusion



1-1. What’s Nuclear Power Generation?

3

Reactor

Boiler

Steam

Steam

Water

Water

Turbine

Condenser

Water Pump

Water Pump

Combustion (Oil, Coal, Gas, etc.)

Nuclear reaction generates heat.

Generator

Grid

To Discharge Canal Cooling Water

Thermal

Nuclear

Electricity generated by a steam driven turbine

Source: Japan Atomic Energy Relations Organization Hitachi, Ltd. 2013. All rights reserved.


1-2. What is BWR?

4

Q: What does “BWR” stand for?

Boiling

Water

Reactor

Answer: B :

W:

R :

What is the merit of boiling water “in” the Reactor?

Quiz 1

Reactor


© Hitachi, Ltd. 2012. All rights reserved. Commercial in Confidence 5

BWR PWR

Suppression Pool

Feed water Pump Circ. Water Pump

Condenser

Turbine Generator

Wat

er

Fuel

Control Rod (CR)

Feed water Pump Circ. Water Pump

Condenser

Turbine Generator

Wat

er

Fuel

Control Rod

Pressurizer

Dem

iner

aliz

er

Dem

iner

aliz

er

Rec

ircul

atio

n P

ump

Steam is generated in BWR Reactor

Reactor

Steam Generators

Steam Steam

Merits of boiling water in the Reactor are … Compact PCV; No Steam Generators Simple Configuration; Direct cycle (only 1 loop) Easy Control; Void Effect can be used for Power Control

Reactor

PCV PCV

PCV: Primary Containment Vessel

1 loop 2 loops

1-3. What is BWR?



We want BWR plant to be …

• Extremely safe

• Cost-competitive

How can we improve the BWR to achieve those?

1. Simpler Configuration Reduce risk ⇒Extremely safe Reduce material Shorten construction period ⇒Cost-competitive

2. Enhancing output power ⇒ Cost-competitive

1-4. Evolution of BWR



1-5. BWRs around the World

7

Vallecitos – USA

Dresden 1 – USA

Laguna Verde - Mexico

Tarapur 1&2 – India

Dodewaard - Netherlands KKM - Switzerland

Garigliano - Italy

Santa María de Garoña - Spain Lungmen - Taiwan

K6/K7 - Japan

KRB - Germany

Source: GE-Hitachi Nuclear Energy International

…94 BWRs generating over 80 TW



1-6. ABWR: Only Operating Gen III+ Reactor

8 Source: NEA “Nuclear Energy Outlook 2008”

Evolutionary BWR technology since late 60’s



ABWR Key Features

Reactor Internal Pump (RIP)

Advanced Human-Machine System

Avoidance of large-size pipe breaking accident potential by adopting RIP

3-system multiplex ECCS

Optimum power control by FMCRD/RIP Intelligent Human-machine Interface

Reducing Station Service Power by adopting RIP

Long Blade Turbine, MSR for High Generation Efficiency

Downsizing Building Volume by adopting RCCV

FMCRD（Electrical and Water Driving）

Digital Instrument and Control System

Safety Improvement

Operational Performance Improvement

Economic Improvement

Reliability Improvement

Reinforced Concrete Containment Vessel

(RCCV)

52” Last Stage Turbine Blade

Moisture Separator Reheater (MSR)

Reactor Pressure Vessel (RPV)

Hitachi GE manufactures major components internally.

Fine Motion Control Rod

Drive (FMCRD)

1-7.

9 Hitachi, Ltd. 2013. All rights reserved.


1-8. Manufacturing Key components

Reactor Pressure Vessel

Core Shroud

Steam Dryer

Moisture Separator

● Fabrication by newest technology and skilled workers

Control Rod Driving Mechanism

Fuel Assembly

Control Rod



◆Equipment :1200-1600 unit ◆ Piping Total Length :100-120Km ◆ Starting Design to COD :9-10years Licensing / Design :4-5 years Construction :4-5 years

Reactor Building ABWR

Turbine Operation Floor

1-9. Engineering with Plant Integrated CAE System

11 Turbine Operation Floor



Computer modeling Site View Simulation Construction Management with 4D simulation

Detail Design

Basic Design

Production Design &

Manufacturing

Construction Operation & Maintenance

Plant Engineering Database EPC Project Experience / Project Management Know-how

1-10. Engineering with Plant Integrated CAE System

12 Hitachi, Ltd. 2013. All rights reserved.





Contents



6. Conclusion



2-1. BWR Performance during the Great East Japan Earthquake

14

All the BWRs other than Fukushima Daiichi (Units 1-4) safely under cold shutdown after the earthquake A key distinction … off-site power was maintained to keep the cores cool and prevent core damage at other NPPs

P

B

A

A

BWRs

ABWRs

ABWRs under construction

PWRs Power stations impacted by the earthquake

Fukushima I

Hamaoka

Ikata

Tokai

Sendai

Genkai

Shimane

Fukushima II

Onagawa

Tomari

Kashiwazaki/Kariwa

Shika

Takahama

Ohi

Mihama

Tsuruga

B B B B B A A

B B B B B B

B B B B

B B B

B B A

B A

B B A

P P P P

P P P P

P P P P

P P P

P P P

P P P

P P

B P

B

Ohma A

X Epicenter

Area affected by the earthquake

A

B

Higashidoori (TEPCO) Higashidoori (Tohoku)



2-2. Fukushima Accident: Sequence of Events

Earthquake 9.0 Mw (moment magnitude) 4th largest in the world on record

Auto-shutdown

Operating reactors shutdown by control rods as designed Loss of off-site power due to the earthquake Emergency diesel generators (EDG) start

Tsunami flooding

Tsunami of approximately 14m above sea level flooded the site Design basis 5.7m

Loss of all Power

Tsunami disabled: emergency diesel generators (EDG) service water system DC batteries, etc.

Loss of Cooling

Loss of DC power Long-term SBO (Station Black Out) LUHS (Loss of Ultimate Heat Sink)

Submerged Tank

Source: TEPCO, GE Hitachi Nuclear Energy International

Top of Reactor Building = 46m above grand elevation



2-3. Strategy for Safety Enhanced ABWR

16

Further Enhancements

based on lessons learned from Fukushima

Safety Enhanced UK-ABWR

Inherent ABWR Safety Features

Diversified water injection methods Large capacity heat sink (pool) Inactivated Primary Containment Vessel Flood-protected DC battery and EDG for SBO mitigation Aircraft crash countermeasures

Additional diversification of power sources Enhance water injection systems and ultimate heat sink Prevent PCV damage Enhance spent fuel pool cooling Backup Building






Contents



6. Conclusion



• GDA Assessment Agreements with ONR/EA have been signed in early April 2013

• GDA Core team in Gloucester and Registered Office in Maidenhead identified and being established

• Mobilisation of technical support team from supply chain underway

• Initial submission on design definition, safety case issues, and PCSR*/GEP-RSR** under development

3-1. GDA Update

CY 2013 2014 2015 2016 2017

Step-1

Step-2

Step-3

Step-4 *PCSR: Pre-construction Safety Report **GEP-RSR: General Environmental Permission-Radioactive Substance Release



3-2. Strategy for early phase of GDA for UK ABWR

19

By having lessons learned in previous GDAs, HGNE has been established strategy for early phase of GDA • Setting up of a UK based core team

- Subject Matter Experts (for 17 technical areas) have been appointed in both HGNE in Japan and Horizon in UK

• Front loading of work programme to address the more technically challenging issues identified in earlier GDAs - List of topical reports to support PCSR and GEP-RSR have been already

discussed with ONR/EA, and submission timeline has been identified - Early preparation of ALARP assessment of what are seen as key challenging

design issues

• Early engagement with regulators to understand their expectations and for HGNE to get early feedback on approaches






Contents



6. Conclusion


© Hitachi, Ltd. 2012. All rights reserved. Commercial in Confidence Hitachi, Ltd. 2013. All rights reserved.

Construction Management Strategy

22

Modularization with Very Heavy

Lift Crane

Open-top & Parallel Construction

Floor Packaging

Construction Work Support System

Front-Loaded Construction Engineering

Detailed Schedule Management

Reduce On-site Work Level On-site Work

Improve On-site Work Efficiency

1 2

3 4 Improve Site Support Work Efficiency

5-1.


Staregy-3: Improvement of On-site Work Efficiency


Basic Design

Detailed Design

Construction

Construction Engineering

Previous Design Process


Basic Design

Detailed Design

Construction

Construction Engineering

Requirements from Construction Engineering Inputs from Plant Design

(BOQ, Composite Design, etc.)

- Just Do It As Planned -

Detailed Construction Management

23

5-2.


Simulation of major large product installation

5-3. Strategy 3: Improve On-site Work Efficiency Crane Simulation






Contents



6. Conclusion



6-1. Conclusion

26

ABWR is a safe, efficient, economical design and meets all current safety requirements of modern plants.

The nuclear industry has and will continue to learn from the unfortunate and extreme events which struck eastern Japan in March 2011.

Based on the extreme events at Fukushima, ABWR has evolved more with lessons learned from Fukushima.



6-2. Conclusion

27

We will provide innovative and competitive ABWR technology with a proven history of successful constructions and operations.

Our effective and efficient construction management has contributed to achieving on-time delivery of similar projects.

We are cooperating with Horizon to ensure the project has a positive impact in the local area, and for local communities.

We are also building our supply chain relationship with Babcock International and Rolls-Royce.


technology overview and gda update - horizon nuclear · pdf filetechnology overview and . gda...

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