testing of fuels and materials for next generation ...€¦ · at the hfr petten nomage4, halden...

Testing of Fuels and Materials for Next Generation Reactors

at the HFR Petten

NOMAGE4, Halden

Presented byJaap G. van der Laan

[email protected]

1.11.2011

20111101 Copyright NRG 2

Contributors

Darina BlagoevaAlexandr FedorovSander de GrootRalph HaniaMonica JongFrodo KlaassenSteven KnolNatalia LuzginovaLida MagielsenArjan Vreeling

... and many others

Teams:• HFR operations• Hot Cells & Laboratories• Engineering & Technology• Physics & Monitoring• Fuels & Isotopes Technologies• Materials Characterization


• The Netherlands Nuclear Infrastructure• HFR Petten• NRG R&D activities • Fuels & materials for next generation

systems• Outlook

Outline


Nuclear Infrastructure in The Netherlands

Amsterdam

Urenco Almelo

NRG ArnhemHOR & TU Delft

KCB Borssele

COVRA

The NetherlandsEurope

NRG Petten

EU JRC

New Built:KCB Borssele 2


The Netherlands Queen’s visit to Kjeller, 1953

Norwegian –Netherlands collaborations started late ’40-ies


New projects

• Delta, the utility currently running the 500 MWe Kerncerntrale Borsele for 60 yrs up to 2033, considers application for construction of a new NPP at the Borsele site.

• The Netherlands Ministry of Economy, Agriculture and Innovation is implementing the appropriate regulatory measures, including staff expansion and training.

• The Netherlands research programme will focus on competencies in wider sense, including education and training, and basic and applied research & development activities: priority on nuclear safety

• In addition the PALLAS project is under preparation: replacement of the HFR at Petten by a state of the art multi-purpose reactor for radio isotope production and nuclear technology developments


Nuclear Infrastructure Petten site

High Flux Reactor Hot Cell laboratory

Actinide laboratory Molybdenum Production Facility


The High Flux ReactorThe HFR is mainly used for

materials & fuels irradiations radioisotopes productionindustrial and medical research

Light water moderated and cooled 45 MWth tank-in-pool multi-purpose testing reactorPlate-type fuel elements with burnable absorber and beryllium reflectorHigh availability: 274 to 291 FPD per year (major repair completed in 2010)

• 20 in-core experiment channelswithin a core arrangement of 9 x 9 positions containing 33 fuel elements, 6 control rods and 22 beryllium reflector elements• 12 experimental positions outside the HFR vessel in the pool-side facility • 4 horizontal beam tubes in use• Gamma irradiation facilities


NRG Activities

• Three main pillars of NRG Fission R&D- Fast Breeder Reactor + P&T- LWR (SCWR)- (V)HTR/Cogeneration.

• This is in line with the European nuclear R&D strategy as laid down by the Sustainable Nuclear Energy Technology Platform (SNETP, vision report available at www.snetp.eu).

• R&D work by NRG is mostly cost-shared by EU and NRG via European framework programs, and/or by national budgets.


NRG Generic topics FRs+P&T

Fuels & materials: Sample fabrication (U, Pu, MA)Irradiation Post-irradiation examinationFuel modelling

Structural Materials:ODS steelsJoining techniquesFracture mechanicsCreep fatigueCorrosion

Core parameters:Uncertainties in nuclear dataEffects of minor actinidesCriticalityShielding

Thermal hydraulics:CFD modelling for fuel rods Heat transfer modelling

Accident analysis:Structural integrity at seismic eventsFuel coolant interactions

System studies and economicsFuel Cycle & nuclear park scenariosCost analysesRoadmapping and visualisation

European Projects:ACSEPT, ADRIANA, ANDES, ESFR, GOFASTR, LEADER, CDT, FAIRFUELS, F-BRIDGE, GETMAT, MATTER

New: PELGRIMM, ASGARD, SEARCH


BODEX project (EU FP6)

Major challeng for transmutation fuels: helium production:- Swelling (fuel-cladding interactions)- He release (pin pressures)Boron Doped EXperiment (BODEX): To study the swelling

effect, boron is implemented to produce helium

+ Quick He production+ Easy handling+ Single effect experiment- Debatable whether it is sufficiently representative

• Inert Matricess: Mo, MgO, YSZ ((Zr,Y)O2)• B- compounds: Mo2B (Mo), Mg3B2O6 (MgO), ZrB2 (YSZ)

S. KnolA. Fedorov

F.C. Klaassen


BODEX project (2)

• Each matrix irradiated at 2 temperatures: 1200 and 800°C• Irradiated in HFR Pool Side Facility to B-10 burn-up ~65% (Total

He: ~6*1020 atoms/cc)

Molybdenum- Large temperature influence, at 800 °C very good performance- Very low helium release

MgO- Large He release, anisotropic swelling

YSZ- Even at high T low swelling- Medium helium release- (High activity)

• PIE still ongoing• Work related to HELIOS experiment with Americium


Fairfuels project (EU FP 7)

NRG conducts two irradiations in 2010-2012 :

• MARIOS (2010-2011)- Blanket fuel (Am0.15U0.85O2-x)- Well-controlled temperatures (1000 oC,

1200 oC)- He release and swelling as a function of

temperature

• SPHERE (2011-2012)- Homogeneous route (Am0.02-0.05Pu0.2O2-x)- In-core behavior of conventional pellet

fuel vs. ‘Sphere-Pac’ fuel forms

• New EU FP7 project: PELGRIMM

F.C. Klaassen(EU Fairfuels coordinator)

R. Hania


Irradiation in LBE

• Lead Bismuth Eutectic, LBE, is the component environment for XADS devices like MYRRHA: compatibility of 316L type and 9Cr steelswith LBE is to be assessed

• Irradiation projects to 2 dpa at BR2 and HFR (tensile/KLST)

• Thick container walls are needed to resist stresses due to swelling of solidified LBE

• Instrumented capsules with 5 thermocouples

• Post-Irradiation Testing undertaken in NRG Fuel-HotCell to allow Polonium handling!

Lida MagielsenSander Kamer


NRG in MATTER IP

Material: 9Cr steelsSet-up is under development

Monica JongNatalia Luzginova


(Very) High Temperature Reactor (1)

• Basis: triso coated UO2 kernels in graphite balls (HTRModul design)

• Initially testing of German and Chinese fuel balls

• Irradiation and P.I.E. for monitoring fission gas release to high burn-up: new sweep-loops installed

• Irradiation and P.I.E. for fuel at VHTR temperature

• Gen4 International Forum collaborative framework

Fuel pebble with graphite shell and thermocouples during assembly

X-ray image of fuel pebble



PYCASSO-I & II:Aim: study the effect of irradiation on coatings, excluding the influence of fuel and fission products at relevant (V)HTR temperatures of 900, 1000 and 1100°CPIE ongoing for Pycasso-I

FE model CEA KAERI JAEA CEA JAEA KAERI1000°C 1100°C 1100°C 1000°C 900°C 900°C

X-ray


Pressure-Vessel• Irradiation of T91 thick section weldment and post-

irradiation fracture toughness and creep (hot vessel option) – derive negligible creep regime

Core structures• Re-installation of graphites qualification tools • Selection and pre-qualification of present day

graphites – high dose HFR irradiations – establish design correlations

Internals & miscellaneous • Ceramic composites for control-rods, e.g. C/C and

SiC/SiC • Composites for support structures, gas duct,

straps, fasteners etc.



Graphite Irradiations (V)HTR

• Fluence rate Øtot = 6-9 E18 m-2s-1

• EDN fluence ~ 5-6 E25 m-2, or ~ 6-7dpa per calendar year

• Ratio min/max ~ 65%• T in range 300 – 1000°C

Main choices:• Modular specimen stacks, well

instrumented, optimum height, 150-200 specimens

• High purity helium purge and graphite foils preventing metallic contamination of specimens

• Irradiation in multiple stages, allowing to obtain full curve by re-irradiation of specimens (to 25 dpa_g)

-7

-5

-3

-1

1

3

5

0 5 10 15 20 25

Neutron Fluence

Rel

ativ

e Vo

lum

e C

hang

e (%

)

FP5FP6

-7

-5

-3

-1

1

3

5

0 5 10 15 20 25

Neutron Fluence

Rel

ativ

e Vo

lum

e C

hang

e (%

)

FP5FP6

Grade Manufacturer Status Coke Process NBG-10 SGL Major Pitch Extrusion NBG-25 SGL Minor Petroleum Iso-moulding NBG 20 SGL Minor Petroleum Extrusion NBG-18 SGL Major Pitch Fibro-moulding NBG-17 SGL Minor Pitch Fibro-moulding PCEA Graftech Major Petroleum Extrusion PCIB Graftech Minor Petroleum Iso-moulding PPEA Graftech Major Pitch Extrusion IG-110 Toyo Tanso Minor Pitch Iso-moulding IG-430 Toyo Tanso Minor Petroleum Iso-moulding LPEB Graftech Minor Needle Extrusion LPIB Graftech Minor Needle Iso-moulding

Arjan VreelingOnne Wouters


A new HTR European FP7 R&D program

ARCHER – Advanced High-Temperature Reactors for Cogeneration of Heat and Electricity Research & Development

The ARCHER project targets generic R&D in the field of (V)HTR technology, in support of demonstration

IP Coordinator:Sander de Groot


Upper Port Launcher:Mirror Thermohydraulics & Remote Handling

Upper Port Viewer:Mirror & Shielding

Vacuum Vessel: qualification of alternative manufacturing methods

Vacuum Vessel: qualification of repair welding

Primary Wall & Shield: bolts for attachments of modules

Primary Wall Modules:Pulsed Heat & Neutron Loads

Primary Wall and Divertor: MIM Tungsten; claddings

Alternative heat-sinks

Test Blanket Modules:• Eurofer qualification• Li ceramics behaviour• Beryllium behaviour• LiPb behaviour• Tritium transport• Instrumentation

And:• Prob. Safety Analyses• Fitness for purpose • Remote Handling• Neutronics• Training etc.

Specials: windows; diagnostics; feedthroughs; instrumentation

Fusion Nuclear Technology at NRG


ITER vessel and in-vessel

Irradiation stress-relaxation of bolt materials

0.0

0.2

0.4

0.6

0.8

1.0

0.0 0.5 1.0 1.5 2.0 2.5 3.0Irradiation dose (dpa) at 300°C

σ/σ

0

16-25% pre-stress uniaxial tensile36-44% pre-stress uniaxial tensile55-65% pre-stress uniaxial tensileBending stripsSTROBO-01 & -02 pre-stress 26-74%STROBO-01 & -02 bending strips

Inlet/outlet manifolds

First wall panel

Hole to fit flexible support

Flexible supports

Vessel

Shield block

Shear key

Gripping hole

Electrical strap

Inlet/outlet manifolds

First wall panel

Hole to fit flexible support

Flexible supports

Vessel

Shield block

Shear key

Gripping hole

Electrical strap

Alloy 625+ and PH13-08 post-irradiation strength

0

400

800

1200

1600

0 0.1 0.2 0.3 0.4 0.5 0.6 0.7

Irradiation dose (dpa)

Yie

ld s

tress

(MP

a)

Yield stress 625+

Yield stress PH13-08Mo


Soon in this theater:

PALLAS, a new nuclear reactor(to succeed HFR)


bringing time forward

testing of fuels and materials for next generation ...€¦ · at the hfr petten nomage4, halden...

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