FUMEXFUMEX--IIIIIIPurposePurpose

Improve predictive capabilities of codes used in fuel behaviour modelling for extended burn-up.

Focus on • Fission gas release • Transient analysis• Pellet to clad interaction (PCI)

at extended burn-up > 60 MWd/kg (LWR) > 20 MWd/kg (PHWR)

But also accident analysis at high bu: LOCA , RIA

FUMEX-III. Area of work needed:PCMI in transient conditionsREGATE Rod Diameter before & after SILOE

9.3

9.35

9.4

9.45

9.5

9.55

9.6

0 100 200 300 400 500 600axial position mm

diam

eter

mm

meas-before Meas-afterPredicted-before Predicted-after

Code predictions for REGATE at 250 mm axial position

9.3

9.35

9.4

9.45

9.5

9.55

9.6

0 1 2 3 4 5 6 7 8 9Code identifier

Post rampafter base irradiation

FUMEX-II results for diametral swelling

• 34 fuel modelling groups • Coordination with OECD/NEA.

• Test cases provided by �Halden Reactor Project, �Commercial irradiations �Tests from participants� Idealised cases (test models at high bu)

• All cases maintained in OECD International Fuel Performance Experimental (IFPE) Database.

FUMEXFUMEX--IIIIII

FUMEX-III Participants: Contracts, Agreements and Observers

TRANSURANUSGermanyTUEV-SUEDW BesenboeckDYN3D GermanyFZDL Holt

COPERNICChinaNPICY Jiao

TRANSURANUSItalyENEAPOLIMI

F VettrainoL Luzzi

TRANSURANUSFUELSIM

ItalyUNIPIA Del NevoFAIRIndiaBARCB Dutta

FUROMTRANSURANUSFRAPTRAN

HungaryAEKIK Kulacsy

COPERNIC3Germany/ France

ArevaM. SperlichENIGMA 5.9BFinlandVTTL KekkonenTRANSURANUSECITUP Van Uffelen

FRAPTRANFRAPCON

CzechNRIM ValachCOPERNICChinaCNPTRT Liu

METEORFTRANAC

ChinaCIAEP Chen,X He

ELESTRESCanadaAECLG ChassieFEMAXIBulgariaINRNE2S StefanovaTRANSURANUSBulgariaINRNES Boneva

BrazilCDTNJ de Mattos

FRAPCONFRAPTRAN

BrazilIPENCNEN/SP

A Teixeira

FRAPTRANFRAPCON

BelgiumTractabelSUEZ

J ZhangBACOArgentinaCNEA2A MarinoDIONISIOArgentinaCNEAA Denis

CodeCountryParticipant

THERMEX-NFORTE

JapanNFIH Kishita

FEMAXI-JNESJapanJNESK Kamimura

FranceOECD/NEAJ GullifordNorwayHaldenT Tverberg

Data Providers and ManagersBISONUSINLR Williamson

FRAPTRANFRAPCON

USPNNLC Beyer

PADFEMAXI

UkraineKIPTO SlyeptsovENIGMA 5.14UKBEJ SheaENIGMA-BUKNNLG RossiterFALCONSwitzerlandPSIG Khvostov

RTOPRussianFederation

SRC TRINITIV Likhanskii

START – 3RussianFederation

VNIIMV Kuznetsov

ROFEMCAREBTRANSURANUS

RomaniaINR G HorhoianuINFRA INFRA-TKoreaKAERIJG Bang

FEMAXI-6/7RANNS

JapanJAEAM Suzuki

CodeCountryParticipant

Participants: FUMEXFUMEX--IIIIII

21 countries: Argentina 2Belgium Brazil 2Bulgaria 2CanadaChina 3Czech RepublicFinlandGermany 2Germany/ FranceHungaryIndiaItaly 2Japan 3KoreaRomaniaRussian Federation 2SwitzerlandUK 2UkraineUS 2EU

NorwayOECD/NEA

FUMEX-III Coordinated Research Project

• Large range of interest � transient behaviour and mechanical interactions, � severe transient behaviour (RIA/LOCA) � temperature and fission gas release at high burnup.

• Large variety of participants �newcomer teams , state-of-the-art code users � reactor systems PHWR, PWR, BWR, WWER

• Some codes are used by several teams : TRANSURANUS, FRAPCON/FRAPTRAN, FEMAXI

FUMEX-III priority cases – First results due June 2010

US 16x16 PWR (TSQ022)

Ginna XO3 segmented pellets

MIR Ramp rods 41, 48, 50 and 51

WWER

US 16x16 PWR (TSQ002 TSQ022)

AREVA idealised case

GAIN Gd701 , 301

IFA535.5 rod809Risø-3 rod II5 52GWd/tU

IFA 519.8/9 Rods DC , DK

FK1 FK2

IFA 650.2

Riso3 GE7;

OSIRIS-2 rod HO9 or J12-5

IFA 629.1

PRIMO rod (BD8)

LWR

Pitesti RO89 RO51AECL NRU (one rod from each ring)

IRDMR FIO-118; FIO-119 (7 rods in total 2+5)

FIO 131

parametric study –failure thresholdINTERRAMP 10 to 20GWd/tU

SUPERRAMPPK6 and PW3 35GWd/tU

2 low BU from Risø-2 GE-m and Risø-3 II3IRDMR FIO-118; FIO-119

CNEA 5 rods (1 undoped)BU15

CANDU

Normal operation FGRGad/NbTransientsLoad follow

transientsRIALOCAPCIPCMI

FGR; Temperature etcSevere transients

Mechanical interaction

MOXPlant type

FUMEX-III: Areas of interest for the modelling teams

AEKI VNIIMNRI KIPTINRNE2 INRNEVTT

INRNEAEKICRCDINRNE2

WWER

ITU UNIPIENEA PSIPNNL SUEZNRI IPENVTT JAEAKAERI BARC

INL ITUUNIPI PSIPNNL SUEZNRI IPENVTT BARCKAERI

INLIPENVTTJNES

VNIIM NNLINL TRINITIPNNL SUEZVTT AREVAJNES KIPTIPEN PSINPIC

INRNEVNIIMJNESINRNE2AEKINPIC

ITU INRNEVNIIM NNLINL PSITRINITI CNEAPNNL SUEZIPEN JNESINRNE2 BARCKAERI NFINPIC

JNESJAEAINRNE2CNEAAEKIKAERINPIC

POLIMI UNIPIVNIIM TRINITICNEA PNNLSUEZ AECLAREVA IPENJNES INRNE2INRNE NPICPSI

ITU INRNEVNIIM NNLINL TRINITICNEA PNNLSUEZ IPENAECL AREVAJNES NFIKAERI INRNE2BARC PSI

ENEAPOLIMIITUNNLJNESNFIJAEACNEAPSI

LWR

INR BARCCNEA2

INR AECLBARC CNEA

INR CNEAAECL BARC

INRCNEA AECLCNEA2 BARC

CNEACANDU

RIALOCANormal

operation FGR

Doped fuels

(Gd; Nb)Transients

Load follow

transientsPCIPCMI

Severe transientsFUMEX-II

FGR; Temperature etcMechanical interactionMOXPlant

type

First RCM: December 2008, held in ViennaProject planned and Priority cases chosen. New data offered.

Second RCM: June 1-4 2010, to be held in Pisa

Discuss priority cases and follow up

FUMEXFUMEX--IIIIII

FUMEX-III Priority case: Unopened rods GE-i & GE-h:

Resulting diameter changes

Power histories during bump test:

FUMEX-III Priority case: GE-7

Resulting diameter change

Axial power distribution

Power history during bump test:

Idealized case from FUMEX-II

Case 27. 2d FANP idealised

0

5

10

15

20

25

0 10 20 30 40 50 60 70 80 90 100Burnup (MWd/kgU)

FGR

(%)

LOCA test HRP

0

2

4

6

8

0 20 40 60 80 100 1200

20

40

60

80

Calculatedhoop strain

Coolant pressure

Measured rod pressure

Calculated rod pressure

Time (s)

Pres

sure

(MPa

)

Strai

n (%)

LOCA test HRP

0

100

200

300

400

500

600

8 9 10 11 12 13 14 15 16

Post-test measurement

TRANSURANUS

Cladding diameter (mm)

Elev

ation

(mm)

NRU LOCA test – MT-4

0

20

40

60

80

0 1000 2000 3000 4000

experimentTRANSURANUS

Permanent tangential strain

Axial Position (mm)

Clad

ding S

train

(%)

MT-4

NRU LOCA test – MT-6A

Uncertainties:Tc ± 6%p0 ± 10%

5000 MC runs

2

6

10

14

0 20 40 60 80 100

TRANSURANUSexperiment

Calc. distributionof rod burst times

Measured intervalof rod burst times

Time (s)

Ro

d pes

sure

(MPa

)

MT-6A

RIA test at NSRR: FK-1 (1/2)

R. Calabrese, Towards nuclear fuel modelling in the various reactor types across Europe with TRANSURANUSBurgas, Bulgaria - Oct. 1, 2009

Mother rodFukushima Daiichi Nuclear Power Station Unit 3 operated by Tokyo Electric Power (TEPCO)BWR 8x8 BJ (STEP I) (active length 360 mm)five operation cycles (1984 1990)

FK-1 segment

16.3 (21.5)16.3 (21.5)average oxide layer (average oxide layer (µµmm))1.51.5FGR (%)FGR (%)

8.5 8.5 ••e+25e+25fast neutron fast neutron fluencefluence (n/m(n/m22))45.145.1average average burnupburnup ((GWd/tUGWd/tU))22.822.8peak linear heat rate peak linear heat rate

(kW/m)(kW/m)

RAI test at NSRR: FK-1 (2/2)

Towards nuclear fuel modelling in the various reactor types across Europe with TRANSURANUSBurgas, Bulgaria - Oct. 1, 2009

NSRR Facility

modified TRIGA type annular reactor, which has the capability of large pulsing power that is increased increases by control rods withdrawal and quickly decreased by the negative feedback of the driver fuel (U-ZrH1.6)

FK-1 pulse

9.59.5••e+04e+04Peak linear heat rate Peak linear heat rate (kW/m)(kW/m)

544544Peak fuel enthalpy (J/g)Peak fuel enthalpy (J/g)4.44.4FWHM (ms)FWHM (ms)