Current Activities on the 4S Reactor DeploymentDesign Specific/4S/Presentations...¾Sodium-cooled...

1 © TOSHIBA CORPORATION 2010, All Rights Reserved.

PSN Number: PSN-2010-0586Document Number: AFT-2010-000134 rev.000(1)

Current Activities on the 4S Reactor Deployment

The 4th Annual Asia-Pacific Nuclear Energy Forumon Small and Medium Reactors: Benefits and Challenges

June 18 and 19, 2010Berkeley, CA, California

Kazuo ArieSenior ManagerAdvanced System Design & Engineering DepartmentIsogo Nuclear Engineering CenterToshiba Corporation

2/30© TOSHIBA CORPORATION 2010, All Rights Reserved.

Outline1. 4S Design Overview2. Technology Development3. Economics4. Licensing5. Concluding Remarks


1. 4S Design Overview2. Technology Development3. Economics4. Licensing5. Concluding Remarks


4S (Super-Safe, Small & Simple)

Reactor

Steam Generator

Turbine/Generator

Sodium-cooled pool type fast reactor

Versions– 10 MWe (30MWt)– 50 MWe (135MWt)

Main features– Refueling interval

10 MWe: 30 years50 MWe: 10 years

– Passive safety– Minimal moving parts– Security and safeguards designed in

R/B located below gradeCo-developer: CRIEPIDeveloping partners: ANL, WEC


Metallic fuel core (U-10%Zr)

Reactivity control by movable reflectors

Shutdown system by reflectors and a shutdown rod

Passive shutdown by metallic fuel properties during ATWS

Electromagnetic pumps have no moving parts

4S Reactor System

IHX

EM Pumps

Core

ReflectorShutdown rod

ATWS: Anticipated Transient Without Scram


IRACScooling system

Heat Transport System

Integrated assembly ofIHX and EM pumps

Passive coolingby RVACS

Helical-coil typedouble-wall steam generator

RVACS: Reactor Vessel Auxiliary Cooling System


Electro-Magnetic Pump (EM Pump)Electromagnetic pump in primary system

– No rotating parts

– Immersed Type

CoilIron core

Duct

Sodium EM Pump


Double Wall Steam Generator (DWSG)Double-wall helical coil type with 30 MWt capacityInner tube leak detection

– Moisture detection in helium between inner and outer tubesOuter tube leak detection

– Helium detection in the intermediate sodium circuit

Sodium

Outer tube

Inner tube

Wire meshand helium

“Development Study of a Wire Mesh Filled Double Wall Tube for FBR Steam Generators”I.Ohshima et.al. Transactions of the Atomic Energy Society of Japan, Vol.36, No.9 (1994)

Sodiumflow

Water flow


Reactor assembly

Rubber

FlangeLeadplug

Horizontal seismic isolatorSeismic isolator

Steam generator

Reactor Building

Ground level


Passive Decay Heat RemovalNatural air draft & natural circulation– RVACS : Natural air draft outside the guard vessel– IRACS : Natural circulation of sodium and air draft at air cooler

RVACS

IRACS (Air Cooler)

Air outlet

Sodium flow

Air flow pass

Guard Vessel

Air inlet

Air inlet

Air outlet

SG

RVACS: Reactor Vessel Auxiliary Cooling System, IRACS : Intermediate Reactor Auxiliary Cooling System

Primary temperature(~260,000sec)

250

300

350

400

450

500

550

0 50,000 100,000 150,000 200,000 250,000

Time (s)

Tem

pera

ture

(℃)

Core-inletCore-outlet

Core temperatureduring loss-of-power

only with natural circulation


ApplicationsElectricity

– Remote area– Mining– Seawater desalination etc.

Steam supply (process heat)– Oil sands/oil shale recovery– Hydrogen production etc.

Potential customers– Alaska, Texas, Hawaii, others (US)– Nunavut, oil sands, mining sites (Canada)– Middle East, Mongoria, etc.


Status of Verification Tests

Design Feature Verification Item Required Testing Status

Long cylindrical core with small diameter

Reflector controlled core

Nuclear design method of reflector controlled core with metallic fuel

Critical experiment

Fuel hydraulic test

Test of reflector drive mechanism

Heat transfer test of RVACS

Sodium test of EM pump/flowmeter

Sodium test of steam generatorLeak detection test

Test of seismic isolator

High volume fraction metallic fuel core

Confirmation of pressure drop in fuel subassembly

Done

Done

Ongoing

Done

Ongoing

Ongoing

Reflector Reflector drive mechanism fine movement

RVACS Heat transfer characteristics between vessel and air

EM pump/flowmeterStructural integrity Stable characteristics

Steam generator(Double wall tubes)

Structural integrityHeat transfer characteristics Leak detection

Seismic isolation Applicability to nuclear plant Done


Shutdown rod

Reflector Controlled Core

Core

Reflector

Reflector controlled core

Photo ; FCA （offered by JAEA）

Critical experiment for 4S core has been successfully performed.

R&D has been performed by CRIEPI in collaboration with JAEA as a part of “Innovative Nuclear Energy System Technology (INEST) Development Projects”under sponsorship of MEXT (JAPAN).


Max temperature 600oCSodium inventory 8 tonSodium flow rate 0 – 12 m3/min

Toshiba Sodium Test Loop Facility

Mother loop area EM pump test area

4S full-scale EM pump


Full-scale Test of EM Pump

Full-scale EM Pump

The performance of the EM pump has been demonstrated for the rated power condition of 4S in February, 2010

Toshiba Test Facility

(This study is a part of “Development of high temperature electromagnetic pump with large diameter and a passive flow coast compensation power supply to be adapted into medium and small reactors of GNEP” funded by METI.)


Electromagnetic Flow-Meter

Configuration of EMF Test Apparatus

magnetic core

exciting coil

annular flow area

inner duct

electrode

sodium

outer duct

magnetic core

exciting coil

annular flow channnel

inner duct

electrode

sodium

outer duct

magnetic core

exciting coil

annular flow area

inner duct

electrode

sodium

outer duct

magnetic core

exciting coil


inner duct

electrode

magnetic core

exciting coil

annular flow area

inner duct

electrode

sodium

outer duct

magnetic core

exciting coil


inner duct

electrode

sodium

outer duct

Full sector test model Sector test model

(This study is a part of “Development of a new EMF in Sodium-cooled Fast Reactor” funded by MEXT.)

Electromagnetic flow-meter (EMF) for 4S EM pump was fabricated, and will be tested using sodium this year.


DWSG Technology

10 meter-long double-wall tubewith wire mesh

(funded by METI)Manufacturing technologies of double-wall tube have been established in 2009.

Section view

Laser welding machine for inner tube

Welded portion of inner tube

Tube inspection technology has been established in 2009.

Small defect (1.0 mmΦ) on outer tube surface has been successfully detected by Remote-Field Eddy Current Technology.

Double-wall tubeAssumed

defect

Eddy current

Exciter coil Detector coil

Direct field

Indirect field

Eddy current


Sodium Tests Schedule

Reflector cavity

10.6m3/min EM pump

EM flow meter

Pre-operation

JFY2010JFY2009JFY2008

Na Test

Design and Fabrication Na Test

Design and Fabrication Installation Na Test

Design and Fabrication Installation Na Test

Design and Fabrication Na Test

(Internal funding)

(MEXT)

(METI)

(Internal funding)

(Internal funding)

Key technologies for 4S will be established by the end of this fiscal year.


Target cost with mass production

10 MWe – 4S : competitive with diesel power plantat remote area

50 MWe – 4S : slightly higher than large LWRs

Economics

To achieve the target,– Reduce on-site construction work by shop fabrication– Mass production– Reduce O&M cost by low maintenance requirements– Simplified spent fuel handling system by long refueling

intervalTo reduce initial financial cost & risk,

– Small reactor– Flexibility to meet increased demand by modular plant

deployment scheme


Shop Fabrication

Site construction

Steel concrete composite

Building(Shop fabrication)

Reactor(Shop fabrication)

BargeConstruction

at site

Shop fabrication reduces site work and its duration


Modular Concept (example)

Low initial costs & riskCost reduction by plant standardization and shared facilities for multiple phases

1st unit4S-135 MWt

Nth unit4S-135 MWt

2nd unit4S-135 MWt

Initial phase

Multiple phase

sharedauxiliary facilities

············

T/G

T/G Electricity

Electricity

T/G Electricity


2007 2008 2009 2010 2011 2012 2013 2014

Licensing Schedule

Design Approval Pre-application Review

Toshiba and WEC are participating in the ANS54.1 WG

▲Design Description▲Long Life Metallic Fuel

▲Seismic Base Isolation▲Safety Analysis

▲PIRT I (Design Base Accident)△Principle Design Criteria

△Emergency Planning△Core Design Analysis

△Aircraft Hazard

ANS54.1 WG

△I&C△PIRT II (Beyond Design Base Accident)

△Safety design△Prevention of Severe Accidents△Plant Dynamics Analysis code

Technical Reporting Plan

▲ Submitted

△ Plan


10CFR50App. A

4S PDC

Evaluate

ANSI/ANS-54.1CRBR SER

PRISMPSER

4S design4S designconceptconcept

Passive LWRlicensing

Accept, modify, or add new criteria

CRBR: Clinch River Breeder Reactor, FSER: Final Safety Evaluation Report, PRISM: Power Reactor Innovative Small Module,PSER: Preliminary Safety Evaluation Report

Development of 4S Principal Design Criteria


No other critical issue in developing 4S PDC based on LWR GDC has been identified except sodium-related matters. GDC for sodium-cooled reactors should be established.

Also, no critical issue has been identified in Regulatory Guides applicability except sodium-cooled reactor matters (not specific to 4S).

The 4S design conformance to the Policy Statement on Regulation of Advanced Nuclear Power Plants has been confirmed.

We are actively participating in ANS 54.1 WG.

Experiences on NRC Pre-review Process


Concluding Remarks4S design incorporates feature such as long-refueling interval, passive safety, low maintenance requirements, and high security.

4S has advantages of ease of operation and maintenance, and flexibility.

10 MWe-4S is now in progress of the pre-application review by USNRC. Toshiba is participating in the activity to establish the LMR regulatory framework. The DA application of 4S to USNRC in 2012 is planned.

Current Activities on the 4S Reactor DeploymentDesign Specific/4S/Presentations...¾Sodium-cooled...

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