application of small fast reactor 4s for energy supply ... · application of small fast reactor 4s...

1 © TOSHIBA CORPORATION 2011, All Rights Reserved.

PSN Number: PSN-2011-1009Document Number: AFT-2011-000225 Rev.000(2)

Application of Small Fast Reactor 4S for Energy Supply Security

IAEA Technical Meetingon Options to Enhance Energy Supply Security

with NPPs Based on SMRsVienna, October 3th - 6th, 2011

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

2/42© TOSHIBA CORPORATION 2011, All Rights Reserved.

Outline1. 4S Design & Safety Features2. 4S Technology Development3. 4S Applications to Enhance

Energy Supply Security4. Conclusion


4S (Super-Safe, Small & Simple)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 design

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

Reactor

Steam Generator

Turbine/Generator


Heat Transport SystemIRACS

Integrated assembly ofIHX and EM pumps

Passive coolingby RVACS

Helical-coil typedouble-wall steam generator

RVACS: Reactor Vessel Auxiliary Cooling System IRACS : Intermediate Reactor Auxiliary Cooling SystemIHX : Intermediate Heat Exchanger

EM pump : Electro-Magnetic pumpEMF : Electro-Magnetic FlowmeterSG : Steam GeneratorFWP : Feed Water Pump


Design ParametersItems 10MWe 50MWe

Type Sodium-cooled pool type fast reactor Sodium-cooled pool type fast reactor

Electric Output 10 MWe 50 MWe

Thermal Output 30 MWt 135 MWt

Number of Loops 1 1

Plant Life Time 30 years 30 years

Fuel life Time 30 years 10 years

Fuel / Clad Material U-10%Zr / HT-9 U-10%Zr / HT-9

Primary Sodium Inlet / Outlet Temperature 355 / 510 degrees C 355 / 510 degrees C

Primary Sodium Flow Rate 547 t/h 2,460 t/h

Intermediate Sodium Inlet / Outlet Temperature 310 / 485 degrees C 310 / 485 degrees C

Intermediate Sodium Flow Rate 482 t/h 2,300 t/h

Steam Generator Inlet / Outlet Temperature 210 / 453 degrees C 210 / 453 degrees C

Steam Pressure (at the outlet of steam generator) 10.5 MPa 10.5 MPa

Decay Heat Removal System RVACS + IRACS RVACS + IRACS

Reactivity Control System Reflector Controlled Reflector Controlled

Primary EM Pump Single stator typelinear annular induction type

Single stator typelinear annular induction type

Intermediate Heat Exchanger (IHX) Helical coil type tube Helical coil type tube

Steam Generator Double wall tube with wire mesh helical coil Double wall tube with wire mesh helical coil


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


No Refueling for 30 Years (10MWe-4S)

Reflector controlled core with metallic fuelLong cylindrical core with small diameter

Fuel U-10%ZrFuel vol. frac. 50%Cladding HT-9235U enrichment（Inner/ Outer）

17 / 19%

Average burn-up

34,000 MWd/t

Inner fuel

Core 2. 5m

Shutdown rod

Outer fuel

Fuel pins

Fixed absorber

Reflector


Key Parameter EBR-II/FFTF * 4S

Peak Burnup, 104MWd/t 5.0 – 20 < 5.5Max. linear power, kW/m 33 – 50 8Cladding hotspot temperature, °C 650 609Peak center line temperature, °C <700 <630Peak radial fuel temperature difference, °C

100 – 250 < 30

Cladding fast fluence, n/cm2 up to 4 x 1023 2 x 1023

Cladding outer diameter, mm 4.4 - 6.9 14Cladding thickness, mm 0.38 – 0.56 1.1Fuel slug diameter, mm 3.33 – 4.98 10.4Fuel length, m 0.3 (0.9 in FFTF) 2.5Plenum/fuel volume ratio 0.84 to 1.45 1.3Fuel residence time, years 1 - 3 30Smeared density, % 75 78

Fuel Design Parameter Comparison

* Irradiation test fuel


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)Prevention of sodium-water reactionInner tube failure monitoring

– Moisture detection in helium between inner and outer tubesOuter tube failure monitoring

– 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


0

200

400

600

800

1000

1200

1400

Isolated base matGround (Design SSE)

0.1 1

Acc

eler

atio

n (g

al)

Period (sec)50.02

h=0.05

0

500

1000

1500

2000

Isolated base matGround (Design SSE)

0.1 1

Acc

eler

atio

n (g

al)

Period (sec)50.02

h=0.05

Floor Response Spectrum- Horizontal -

Acceleration response for horizontal direction during earthquake can be significantly reduced by seismic isolator.

It contributes to flexibility of site selection as well as simplification of equipment design.

Effect of Seismic Isolator Floor Response Spectrum

- Vertical -


Site Layout and Used Fuel Management

Typical plot plan and used fuel storage plan for the 10MWe-4S

Dry cask storage

area

0M 25M 50M

Used fuel will be cooled in reactor for one year and then stored in dry cask for the 10MWe-4S. There is no need for used fuel pond.Used fuel pond is needed for the 50MWe-4S, since the refueling is done every ten years.

Reactor Buildingo 29 m Long (95 ft)o 24 m Wide (79 ft)o 22 m High (72 ft)


Shop Fabrication (modular construction)

Site construction

Steel concrete composite

Building(Shop fabrication)

Reactor(Shop fabrication)

BargeConstruction

at site

Shop fabrication reduces site work and its duration


300

400

500

600

700

800

900

0 60 120 180 240 300 360Time (s)

Fuel

Cladding

CDF = 4.3 x 10-4

Tem

pera

ture

(°C

)

PCT = 743 (°C)

CDF : Cumulative Damage FractionPCT : Peak Cladding Temperature

Passive Shutdown Capability

-0.3

-0.2

-0.1

0.0

0.1

0 60 120 180 240 300 360Time (s)

NetCladdingDopplerFuelCoolantRadial core expansionReflector/core displacement

Rea

ctiv

ity ($

)Net

Coolant0.0

0.2

0.4

0.6

0.8

1.0

1.2

0 60 120 180 240 300 360Time (s)

PowerPrimary flow

Nor

mal

ized

Pow

er a

nd F

low

(-)

Passive shutdown is achievedby negative reactivity feedback.

Anticipated Transient Without Scram (ATWS)(Unprotected loss of flow)


RVACS

IRACS (Air Cooler)

Air outlet

Sodium flow

Air flow pass

Guard Vessel

Air inlet

Air inlet

Air outlet

SG

RVACS

IRACS (Air Cooler)

Air outlet

Sodium flow

Air flow pass

Guard Vessel

Air inlet

Air inlet

Air outlet

SG

Passive Decay Heat RemovalNatural air draft & natural circulation

RVACS : Natural air draft outside the guard vesselIRACS : Natural circulation of sodium and air draft at air cooler

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


0

100

200

300

400

500

600

0 5 10 15 20 25Time (h)

Tem

pera

ture

(℃)

Core outlet

Analysis results of heat removal after aircraft crashRVACS and IRACS stacks destroyed by crash of aircraft Intermediate and feedwater pumps trip Reactor shut down IRACS not availableFor RVACS, 50% of the cross-section of air flow path blocked

IHTS

WSSReactor

SG Condenser

Secondary Intermediate EM pump

Top dome

Core

IHX

Primary EM pump

IRACS

A/CRVACS

Dump tank

IHTS WSSRVACS

SG Condenser

Intermediate EM pump

Top dome

Core

IHX

Primary EM pump

IRACSA/C

PHTS

Dump tank

IHTS

WSSReactor

SG Condenser

Secondary Intermediate EM pump

Top dome

Core

IHX

Primary EM pump

IRACS

A/CRVACS

Dump tank

IHTS WSSRVACS

SG Condenser

Intermediate EM pump

Top dome

Core

IHX

Primary EM pump

IRACSA/C

PHTS

Dump tank

X X

Core outlet temperature

Core Cooling after Aircraft Crash


Containment for Radionuclide

Guard vessel

Top DomeFuelFuel claddingReactor vessel (trap effect by sodium)Containment

Guard vesselTop domeMitigation of sodium fire by nitrogen gas inside the top dome

Reactor building

N2 gas


Dose Rate Evaluation (1/2) 4S source term

*J.K.Fink et al.,”Thermophysical Properties of Sodium” ANL-CEN-RSD-1 (1971)**C.G.Allan et al.,” Solubility and Deposition Behavior of Sodium Bromide and SodiumIodine in Sodium / Stainless Steel Systems” TRG Report 2458(D) (1973)***B.D.Pollock et al.,”Vaporization of Fission Product from Sodium” ANL-7520 Part-1 (1968)

1.0E-11

1.0E-10

1.0E-09

1.0E-08

1.0E-07

1.0E-06

1.0E-05

1.0E-04

1.0E-03

200 300 400 500 600 700 800 900

Sodium temperature[℃]

Rele

ase fra

ction[-

]

Na

NaI

Cs

*

**

***

Release fraction of sodium, NaI and Cs to cover gas Release fraction from core into cover gas

Release Fraction from Core into Cover Gas

1.0E-09

1.0E-08

1.0E-07

1.0E-06

1.0E-05

1.0E-04

1.0E-03

1.0E-02

1.0E-01

1.0E+00

Noble

Gas

es

Haloge

nsAlka

li Meta

ls

Te Grou

p

Ba, Sr

Noble

Metals

Ce Grou

pLa

nthan

ides

Rele

ase

Fra

ction

4S case (Core inventory fraction released into Top dome)

LWR case ('PWR core inventory fraction released into containment', R.G.1.183)


0M 25M 50M0M 25M 50M

Protective action initiation dose

(US EPA)10mSv

Total equivalent dose at 200m from

reactor building（one month

cumulative value）

5mSv

Reactor Building

Assumptions10MWe-4SAll fuel cladding failureConservative assumption of radionuclide trap by sodium in reactor vessel (RV)radionuclide leak rates from RV: 10%/dayradionuclide leak rates from containment: 1%/day

Result

Dose Rate Evaluation (2/2)

Turbine Building


Safety Related Issues 4S’s safety design to mitigate and prevent from severe accident

Station black out (SBO)Core damage is avoidable without any emergency power supply by passive decay heat removal system with natural circulation, not necessary the pump. There is no limitation for duration time.

Earthquakes Supporting the reactor building by seismic isolator.

Aircraft hazard Constructed under ground.

Tsunami / Flood

Redundant shutdown system and passive decay heat removal system without external power supply and emergency power system. Reinforced reactor building to protects from massive water invasion by keeping its water-tightness.

Spent fuel poolNo need for spent fuel pool due to long-term cooling (about 1 year) after the long-term operation (i.e., 30 years) and then stored in dry cask for the 10MWe-4S.

Final heat sink in emergency situations

Air is the final heat sink (RVACS and/or IRACS), not depends on water and any emergency power (passive decay heat removal system).

Containment system reliability Containment system is consisted of top dome and guard vessel.

Safety Features Related to Fukushima Accident


1. 4S Design & Safety Features2. 4S Technology Development3. 4S Applications to Enhance



Status of Technology Development

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 Done

High volume fraction metallic fuel core

Confirmation of pressure drop in fuel subassembly Fuel hydraulic test Done

Reflector Reflector drive mechanism fine movement

Test of reflector drive mechanism Done

RVACS Heat transfer characteristics between vessel and air

Heat transfer test of RVACS Done

EM pump/flowmeterStructural integrity Stable characteristics

Sodium test of EM pump/flowmeter Ongoing

Steam generator(Double wall tubes)

Structural integrityHeat transfer characteristics Leak detection

Sodium test of steam generatorLeak detection test

Ongoing

Seismic isolation Applicability to nuclear plant Test of seismic isolator 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.)


Power supply control system

VVVF Power source

EM pumpFW

SMEx R

EC

Current of VVVF

Backup power supply

Current of Backup power supply

Shutoff switch

Normal bus

0

2

4

6

8

10

12

0 10 20 30 40 50 60時間[s]

流量

[m3 /

min

]

半減時間15秒

5.3

10.6

VVVF： Variable Voltage Variable Frequency, Ex： Exciter,

REC： permanent magnet rectifier, SM： Synchronous Motor, FW： Fly wheel

Shutoff switch

Required flow coast down characteristic can be obtainedby the backup power supply system during reactor trip.

Flow

rate

(m3 /m

in)

Dynamic characteristic analysis

Time (sec)

Reduction by half time of flow

Control circuits are unnecessary by using a permanent magnet exciter.

Backup Power Supply for EM pump


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


ApplicationsIndependent 4S System (base applications)

Electricity/heat supply for remote area communityElectricity supply for mining siteHot steam supply for oil sands/oil shale recoveryElectricity supply for seawater desalinationElectricity/heat supply for hydrogen production

Hybrid System by Combination of 4S & Smart Grid & Energy Storage System

Flexible energy supply for remote areaSecured energy supply for "critical" areaElectricity/heat/water/hydrogen supply as a social infrastructure


Current electricity priceat Nunavut Communities

In Canada$0.39 - $0.94 per kwh

Electricity Supply for Remote Area

(Map: State of Alaska, Japan Office)

◎Galena

◎Seward

◎Nome

◎Bethel

◎Point Hope

◎Unalaska

◎Barrow

◎Red Dog

◎Donlin Creek

◎◎◎

◎Ft. GreelyPS. 9

G. Fairbanks

Ft. Wainwright

◎Galena

◎Seward

◎Nome

◎Bethel

◎Point Hope

◎Unalaska

◎Barrow

◎Red Dog

◎Donlin Creek

◎◎◎

◎Ft. GreelyPS. 9

G. Fairbanks

Ft. Wainwright

Current electricity priceat remote area

in Alaska$0.30 – over $1 per kwh

(Doyon, Limited Report, January, 2009) (Radix Corporation, ANS annual meeting 2010, San Diego)

(Map: http://www.threecordministries.org/ArcticMaps.htm)


Hot Steam Supply for Oil Sands

SOURCE: Suncor, www.suncor.com

Source: www.neb-one.gc.ca

SAGD plants require high temperature (approx. 300 C) steam which can be supplied by fast reactor.

Oil Sand SAGD(Steam-Assisted Gravity Drainage)


Oil Sands Recovery - Required Energy -Project Production

[b/d]Thermal[MWth]

Project Production[b/d]

Thermal[MWth]

Chevron Canada Ellis River 100,000 767 KNOC BlackGold 20,000 153CNRL Birch Mountain 30,000 230 Laricina Germain 1,800 14

CNRL Gregoire Lake 30,000 230 MEG Christina Lake 23,880 183CNRL Kirby 30,000 230 NAOSC (Statoil) Kai Kos Dehseh 140,000 1073CNRL Leismer 15,000 115 Nexen Long Lake 72,000 552CNRL Primrose/Wolf Lake 120,000 920 Nexen Long Lake South 70,000 537Connacher Great Divide 10,000 77 North Peace Energy Red Earth 1,000 8ConocoPhillips Surmont 25,000 192 Patch Ells River 10,000 77

Devon Jackfish 35,000 268 Petrobank (Whitesands) 90,000 690EnCana Borealis 32,500 249 Petro-Canada Chard 40,000 307EnCana Christina Lake 30,000 230 Petro-Canada Meadow Creek 40,000 307EnCana Foster Creek 30,000 230 Petro-Canada Lewis 40,000 307Enerplus Kirby 25,000 192 Petro-Canada MacKay River 40,000 307Husky Caribou Lake 10,000 77 Shell (BlackRock) Orion (Hilda

Lake)10,000 77

Husky Sunrise 50,000 383 Shell Peace River 50,000 383Husky Tucker 30,000 230 Suncor Firebag 68,000 521

Imperial Oil Cold Lake 30,000 230 Total (Deer Creek) Joslyn 15,000 115JACOS Hangingstone 25,000 192 Value Creation Terre de Grace 40,000 307

Larger than 270 MWt 960,000 7,361Smaller than 270 MWt 469,180 3,599

Assumption: 230[MWth] for 30,000[b/d]


Seawater Desalination - Required Energy -Plant Capacit

y[m3/d]

EPC[MWe]

Pant Capacity

[m3/d]

EPC[MWe]

Nassau, Bahamas 10,000 3 Tuas, Singapore 136,380 40.5

Dhekelia I, Republic of Cyprus 20,000 6 Alger East, Algeria 100,000 30

Dhekelia II, Republic of Cyprus 40,000 12 Alger West, Algeria 100,000 30

Barbados, Barbados 30,000 9 Oran, Algeria 100,000 30

Larnaca, Republic of Cyprus 54,000 16 Skikda, Algeria 100,000 30

Point Lisas, Trinidad and Tobago 113,000 33.5 Yantai, China 120,000 36

Hermosillo, Mexico 128,690 36.5 Yantai 2, China 160,000 47.5

Tampa Bay, U.S. 94,625 28 Sinai, Egypt 113,650 34

Ashdod, Israel 123,290 36.5 Chennai, India 15,000 4.5

Haifa, Israel 123,290 36.5 Gaza, Palestine 60,000 18

Palmahim, Israel 123,290 36.5 Limassol, Republic of Cyprus 40,000 12

Shomrat, Israel 123,290 36.5 Nassau, Bahamas 22,500 7

Carmel, Israel 83,270 25 Antofagasta, Chile 52,000 15.5

Caesarea, Israel 136,260 40.5 Corpus Christi, U.S. 95,000 28

Haifa, Israel 123,290 36.5 Freeport, U.S. 95,000 28

Sohar, Oman 136,380 40.5 Moss Landing, U.S. 45,000 13.5

Shuqaia, Saudi Arabia 94,625 28 Moss Landing, U.S. 80,000 24

Total 2,991,830

890

Desalination plants require electric power that is less than 50 MWe： 22,370,000[m3/d] SOURCE: JAIF, The Status of Desalination and Challenge for Nuclear Power Plant, and Pacific Institute, The World's Water 2006-2007


Electricity Supply for Seawater Desalination

4S (Electricity)

Desalination plant

Fresh water production rate168,000 m3/day (50MWe-4S)

Two Stage Reverse Osmosis membrane


Electricity/heat Supply for H2 ProductionHTE: High Temperature Electrolysis CellsHydrogen Production from H2ORequired Temp.： 500oC Production Rate

3,000 Nm3/h (10MWe-4S) 15,000 Nm3/h (50MWe-4S)

O2

Elec

trol

yte

Cat

hode

Ano

de H2O

H2

O2- e-e-

High Temperature Steam Electrolyser

(Solid Oxide Electrolyte Cell)


Hybrid System (4S + Smart Grid + Energy Storage)

Smart Grid

electricityheat

electricity4SDesalination Energy

Storage

electricityheat

hydrogenwater

Community Transportation

electricityheat


Increased Capability of Electricity Supply4S + Smart Grid + Energy Storage 4S system onlyElectricity

Demand Control

Range by 4S Bypass Function

Load Curve/Summer Load Curve/Winter

4S Power Range (Turbine Bypass Function)

0 6 12 18 24 0 6 12 18 24Hour Hour

Demand Control

Range by Hybrid System

Capability of electricity supply of 4S can be increased by the combination of [4S + Smart Grid + Energy Storage] system.It contributes to expansion of 4S application to larger cities and a backup energy system for important "critical" area.Considering such combination of energy storage system and desalination, 4S-based Hybrid System could be a key social infrastructure.


Current Density [A/cm2]

Cel

l Vol

tage

[V]

0.4

0.6

0.8

1.0

1.2

1.4

-1.5 -1.0 -0.5 0.0 0.5 1.0 1.5

Toshiba H2 Energy Storage Technology

H2 Energy Storage System

H2 Storage Tank

Energy Conversion Cell(H2 <--> Electricity)by SOFC & SOEC

SOFC: Solid Oxide Fuel CellSOEC: Solid Oxide Electrolysis Cell

Measured I-V Performanceon Toshiba Solid Oxide Cell

Ve Vf

SOFC mode(electricity production)

SOEC mode(hydrogen production)

Electrochemical Voltage Efficiency（EVE）, Vf/Ve=0.95


Conclusion4S design incorporates distinguished features such as long-refueling interval, passive safety, low maintenance requirements, and high security.

4S-based Hybrid System along with its enhanced nuclear safety could be a key social infrastructure for energy supply security by combination with smart grid, energy storage system and so on.

application of small fast reactor 4s for energy supply ... · application of small fast reactor 4s...

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