National Status on LFR Development in USA - Smith

7/30/2019 National Status on LFR Development in USA - Smith

1/21

NationalStatusofLFR

Development:USA

CraigF.Smith

NavalPostgraduateSchool,USA

Seminar:ActivitiesforLeadcooledFastReactors(LFR)inGenerationIVInternationalForum(GIF)

Tokyo

Institute

of

Technology

November9th,2012


2/21

Historicalbackdrop:LMFRs

Closingcomments


3/21

USFastReactors:

ARich

Historical

Context

emen ne: e rs as reac or, u y n . u ue e ,mercurycooled,25Wtpower.

EBR1:

the

first

reactor

to

generate

electrical

power,

built

in

1949

a a o a s. a coo e , . , ecomm ss one n .Firstbreederreactor.

Fermi1:94MWeFBRprototype,builtnearDetroitin1957,

operate

unt

.

o um

coo e . LAMPRE:1 MWt FRbasedonmoltenPu fuel,sodiumcooling,andreflectorcontrol,builtatLANLinthe195761timeframe.

EBRII:sodiumcooled62MWt reactor,builtinIdahoastheIFRprototypein1965;operatedfor30years.

SEFOR:Ex erimental

test

reactor

o erated

from

1969

to

1972

in

Arkansas.MOXfueled,Nacooled,20MWt.

FFTF:Builtin1978inWashingtonState,400MWt Nacooledtestreactor.


4/21

Clementine

1946

EBR1

1951

Fermi1

EBR2

1965

SEFOR

1972

FFTF

1978


5/21

ofliquidmetalcoolants

Coolant Melting Boiling Chemical

( C)

( C) (w/Air and Water)

Lead-Bismuth 125 1670 Inert

(Pb-Bi, LBE)

Lead (Pb) 327 1737 Inert

Sodium (Na) 98 883 Highly reactive

LeadandLBECoolantsProvidePromisingOverallCharacteristics

5


6/21

Goals achievable

oal Areas v a n r ns c coo an proper es p usEngineering

Sustainability

Transmutation of MA

Sim licit

Economics

Compactness

Primary system at atmospheric pressure

Safety and Reliability No risk of re-criticality in case of core melt(to be confirmed by severe accident analysis)

Chemical inertness/high margin to boiling

Proliferation

Resistance and

Use of fuel containing MA

Use of non-reactive coolantys ca ro ec on Sealed core and/or long refueling cycle

6


7/21

LFRActivitiesintheUS

LFRactivitiesintheUShave

pastfewyears

Continuing(thoughmainly

Workat

US

national

laboratories

Universityefforts

Some

US

industrial

efforts asa re erence

conceptforasmall,


8/21

Reactor (SSTAR)

CLOSURE HEA D

CONTROLRODDRIVES

SSTAR is a small natural

circulation fast reactor of 20

CO 2 INLET NOZZLE

(1 OF 4)

(1 OF 8)

- -

CONTROL

ROD GUIDE

TUBES ANDDRIVELINES

THERMAL

MWe/45 MWt, that can be

scaled up to 180 MWe/400

MWt.

EXCHA NGER (1 OF 4 )

FLOW SHROUDGUARDVESSEL

The compact active core is

removed by the supplier as a

ACTIVE CORE ANDFISSION GAS PLENUM

RADIAL REFLECTOR

FLOW DISTRIBUTOR

REACTORVESSEL

s ng e casse e an rep ace y

a fresh core.

Key technical attributes include the use of lead (Pb) as coolant and along-life sealed core in a small, modular system.

8


9/21

Coolant Lead

Fuel Transuranic Nitride,

Peak FuelTemperature, C

841

nr c e n 15

Enrichment, % 5 Radial Zones,TRU/HM 1.7/3.5/

Peak CladdingTemperature, C

650

Fuel Pin Diameter, 2.50. . .

Core Lifetime,years

15-30

m

Fuel/Coolant VolumeFractions

0.45/0.35

Core Inlet/OutletTemperature, C

420/567

Coolant circulation Natural convection

Active CoreDimensions,

Height/Diameter, m

0.976/1.22

Average (Peak)Discharge Burnup,

81(131)Power conversion S-CO2

Brayton cycle

9


10/21

intheUS

Effortsat

US

national

labs

Generation IV Nuclear Energy SystemsSystem Research Plan

LLNLsupporttoDOEs

AdvancedReactorprogram

for the Lead-cooled Fast Reactor

Pre arin Toda for Tomorrows Ener Needs

theSUPERSTAR

concept,

an

extensionoftheSSTAR

concept

LANL

work

with

MIT

and

wit UCBer e eyonmateria

testingandperformance.

Issued by the

Generation IV International Forum

LFR Preliminary System Steering Committee


11/21

n vers ye o r s

MIT

work

on

FunctionallyGraded

Com ositematerials

UC

Berkeley

material

2m3m

Schematic vertical cut through the ENHS reactor

work30m

27m

8m

3m

2m

Number of Stacks = 4

Cross Section of Stack

Seismic isolators

opera on

o

an

LBEloop3.64m (O.D; t=0.05)

17.6

25m

ENHS module

Reactor pool

Steam generators6.94m (I.D.)

Underground silo

Reactor Vessel Air

Cooling System (RVACS)


12/21

ome m e n us r a e o r s n e

Hyperion

Power

Group

(HPG)

(now

Gen4Energy)

lakeChime PPRS


13/21

GenIVInternationalForum(GIF):Current

Statuswith

regard

to

LFR

re m nary ys em eer ng omm ee p was orme n

2005 MembersincludedEU US Ja anandKorea

PreparedinitialdraftLFRSystemResearchPlan(LFRSRP)

Systemsincludedalargecentralstationdesign(ELSY)andasmall

In2010,

an

MOU

was

signed

between

EU

and

Japan

causing

a

reformulationofthepSSC

In2011,theRussianFederationaddeditssignaturetotheMOU

InApril,2012,thereformulatedpSSC metinPisaandbegunthe

processo rev s ng e

ThenewpSSC envisionsvariousupdatestothecentralstation

300)as

a

new

thrust

in

the

SRP


14/21

InspiteofarichhistoryinLMFRdevelopment,

currentUS

efforts

related

to

LFR

are

limited

Nevertheless,thereiscontinuinginterestin

,

theSFR

Asmallbutdedicatedgroupofresearchersare

continuin to maintain o tions throu h

nationallab,universityandindustryprojects.


15/21

BACKUPSLIDES


16/21

MITWorkonFunctionallyGraded

Composites(FGC)

O jective: esignan pro uce ue c a ingan coo antpiping orHLM

cooled(Pb/LBE)fastreactorsusingcommercialpractices.

TheFGC

consists

of

a

structural

layer

of

a

9Cr

1Mo

steel

(T/F91)

and

a

corrosionresistantprotectivelayerofanewalloywithacompositionof

Fe12Cr2Si.

ExtendsO eratin Tem eratureto700CandFlowVelocit to

6m/sec

Theprojectproceededtothepointof

(TREX)productforbothODandID

cladmaterial.

developmentandfurtherdevelop

thepropertiesdatabase.

16


17/21

The FGC protects against LBE corrosion in all expected environments, oxidizing or

reducing, such that corrosion is no longer a concern for Pb/LBE-cooled systems.

Extrapolated corrosion rates based on the experiments are less than 1 m/yr , which is

negligible for structural components, assuming a 60 year reactor lifetime.

The FGC is diffusionally stable. The diffusional dilution zone between the two layers will

not exceed 17 mm for fuel cladding (three year life) or 33 mm for coolant piping (sixty

year e , o assume o opera e a .

Because of these performance gains, the FGC represents an enabling technology for

Pb/LBE-cooled reactors and systems. A steady-state temperature increase of up to 150C

,

materials exist.

The FGC is ready for immediate deployment in non-irradiated or low-dose applications.

The corrosion resistance has been demonstrated, and will be verified endin lon erlength experiments.

17


18/21

UCBerkeleycontinueswithother

mater a san

es gn

wor

UseoftheICE2ex erimentalstationtoinvesti atetheeffectsof

irradiationoncladdingsteelcorrosioninhightemperature

chemistrycontrolled

heavy

liquid

metal

environment

(collaborationwithLANL)

TestingHT9steelinLBEatLANLsIonBeamMaterialsLab(IBML)

~

5wt%oxygen).

o Testedsensorequipmentunderirradiationconditions.

o PIEtobecarriedoutatUCBerkeleyduring 2012.

Testing

commercial

oxygen

sensors

in

HLM Comp ete mec anica testingo oxi e ayersto eterminet e

fracturestressneededtospallofftheoxidelayer

andburn

(B&B)

core

concepts.


19/21

-promoting its HPM system

Power 70MWt, 25MWe

Lifetime 8 10 ears

Size (m) 1.5w x 2.5h

Weight (T) Less than 50

Coolant PbBi

Fuel uranium nitrideEnrichment


20/21

TheSTARENHS(EncapsulatedNuclearHeatSource)

3yearNERIstudywithUCB,ANL,

CRIEPIcompletedinFY02

Evolutionaryconcept

developed

fromCRIEPIToshiba4Sreactor

Naturalcirculationcooling

Reactorcore

heat

transferred

from

primarytosecondaryPbBithrough

capsu ewa

Fuelcontainedincapsule

Engineeringfeasibility

demonstratedbuteconomic

feasibilityisuncertain


21/21

Lakechime PPRS is pursuing concepts

described as Evolutionary SSTAR

E-SSTAR

Evolutionary SSTAR variation intended toemphasize early deployment; currently at

proposal stage. Features may include:

Forced cooling Oxide fuel

Steam cycle power conversion

Small reactor

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Documents

National Status on LFR Development in USA - Smith