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French-Swedish Seminar on Future Nuclear Systems -K TH -3rd December 2013

The JHR project : a new High Performances European MTR

(Material Testing Reactor) with modern experimental

capacities : toward an International User Facility

Dr Gilles Bignan; Christian Gonnier

CEA / Nuclear Energy Directorate (France)

Contact: [email protected]


Plan of the presentation

- Context (why a new MTR ?)

- Generalities

- Status of the building project

- Experimental capacities (enhancement of on-line instrumentation)

- Operating Rules -Secondee Program (including VR-CEA agreement)

Jules Horowitz 1921-1995

Pioneer and leading expert

in nuclear and reactorPhysics (CEA)


MTR allows to reproduce on a small scale, real power plant conditions and in some cases, more severe conditions for

Material screening (comparison of materials tested under representative conditions)

Material characterisation (behaviour of one material in a wide range of operating conditions, up to off-normal and severe conditions)

Fuel element qualification (test of one / several fuel rods (clad+fuel))

What are the Objectives of an MTR (Material Testing Reactor) ?



AGEING MATERIAL TEST REACTOR (MTR) FLEET IN EUROPE

HBWR

HFRBR2

OSIRISLVR-15

MARIA

JHR

PHENIX

Under construction

Age of current E.U. main MTRs

in 2011 (years)

BR2 (B) 48HALDEN (N) 51HFR (NL) 50LVR 15 (CZ) 54MARIA (PO) 38OSIRIS (F) 45PHENIX (F) shutdownR2 (S) shutdown


JHR:A new MTR funded and steered

by an international Consortium

� JHR International Consortium:� A European Framework with International Partners (India, Israel, Japan)� Industrial Partners ( France, Sweden , Spain, Finland…)� Operation Rules allows flexibility for :

� Implementing bilateral programs with full property of results� Participating to Multilateral Programs open to non Consortium Members

� CEA is mandate by the Consortium to promote JHR and its ancillary labs to the International Community and to build interna tional joint Programs

The 12 JHR Consortium Members (May 2013) :

IAEC

Associated Partnership: JAEAMarch 2013 : UK/CEA agreement; NNL istaking the role of the UK representative to

JHR


R&D in support to nuclear Industry Safety and Plant life time management (ageing & new plants)Fuel behavior validation in incidental and accident al situationAssess innovations and related safety for future NP Ps (either LWR or GENIV concepts)

Radio-isotopes supply for medical application MOLI production

JHR will supply 25% of the European demand (today about 8 millions protocols/year) and up to 50% upon specific request

JHR will be a key tool to support expertise (ESFRI Label)Training of new generationsMaintaining a national expertise staff and credibility for public acceptanceAssessing safety requirements evolution and international regulation harmonisation

JHR 3 MAIN OBJECTIVES


60

cm

Hot cells and storage pools (Non destructive examinations)

FP lab and experimental

cubicles

Reactor pool Core and

reflector(60x60 cm2)

JHR General presentation

Cycle Length : 25 to 30 daysPower : 70 Mth to 100 Mth


Thermal Neutrons flux In reflectorJHR: 5.5 1014 n/cm².s

and 6 displacement systemsOSIRIS: ~ 1.5 1014 n/cm².sand 1 displacement system

Displacement systems in JHR to:• Adjust the fissile power• Study transients

Material ageingJHR : up to 16 dpa/y OSIRIS : ~ 5 dpa/y

Fast neutrons flux in core

JHR: 5.5 1014 n/cm².sOSIRIS: 1.5 1014 n/cm².s

In JHR : -Highly Instrumented

Experiments- On-line fission

Gas analysis- 20 simultaneous

experiments

JHR : experimental capacity & performances

at 100 MW power level (*) (*) 70 MW operation also possible


piping

penetration

cubicle ;

Control of Thyconditions and water treatment

Connection

lines

FP piping

penetration

Reactor

vessel

Quantitative online gamma spectrometry

reservation

JHR experimental capacitygeneral architecture of an experimental loop:

in-pile test device and out-of-pile device

Test device

FP laboratory

cubicle dedicatedto on-line FP measurement


JHR experimental capacity, general characteristics the core

| PAGE 10

In reflectorUp to 5.5 1014 n/cm².s~20 fixed positions

(F100mm ; 1 position F 200mm)

and 6 displacement systems

Fuel studies: up to 600 W/cm with a 1% 235U PWR rod

In coreUp to 5.5 1014 n/cm².s > 1 MeVUp to 1015 n/cm².s > 0.1 MeV

Displacement systems:• Adjust the fissile power• Study transients

Fuel experiment(fast neutron flux – GEN IV)

7 Small locations (F ~ 32 mm)3 Large locations (F ~ 80 mm)

Material ageing(low ageing rate)

~20 simultaneous experiments

Core Designed for UMo-Al fuel Start-up with U 3Si2-Al fuel

70 MWth / 100 MWth25 to 30 days cycle length

6-7 days shutdown

0

0.05

0.1

0.15

0.2

0.25

1.0E-09 1.0E-07 1.0E-05 1.0E-03 1.0E-01 1.0E+01

E [MeV]

1/L

etha

rgy

Position 103Position 101Position C313SFR core reference

Material ageing(up to 16 dpa/y)

GEN II & III + GEN IV

Thermal neutron flux Fast neutron flux

The core is under moderated => high fast neutron flux in the coreand high thermal neutron flux in the reflector


JHR experimental capacity experimental equipments: Non Destructive Examinatio ns

5 DÉCEMBRE 2013

Initial checks of the experimental loadingAdjustment of the experimental protocol

Final NDE after the irradiation phase


JHR experimental capacityexperimental equipments: displacement systems

Real time feed back of the advance velocity based on SPNDs measurement

Stop order based on thermal balance with anticipation of dynamic effect

total length : 450 mm

linear power of 620 W/cm for UO2 fuel reachable with 1,3% U5 fuel

V ~5mm/s (600W/cm/mn 1%U5)V back ~50mm/s

• Steady state conditions (long term irradiation)• Power cycling (load follow)• Power ramps

Accurate power control of the experiment


An additional objective : medical applications ( 99Mo)

5 DÉCEMBRE 2013

Devices dedicated

to 99Mo production

Moving boxes

Devices in reflector

Devices in core

Reactor Pool View

Production capability: 25 to 50% of EU needsProduction capability:25 to 50% of EU needs


JHR Status JHR Status JHR Status JHR Status

of the Building Projectof the Building Projectof the Building Projectof the Building Project


GENERAL VIEW OF JHR BUILDING SITE-SPRING 2013

L = 51 metersL = 47 meters

ϕ = 35 meters


Building Site (September 2013)

5 DÉCEMBRE 2013


EXAMPLES OF IN-KIND CONTRIBUTIONS FROM JHR CONSORTIUM PARTNERS

Hot cells supplied by NRI (CZ)

Mockup at NRI-Rez

Underwater photonic imaging system(X-Ray and gamma tomography)

supplied by VTT (FI)

The MELODIE sample-holder(biaxial mechanical loading on a material

sample)supplied by VTT (FI)

VTT sample-holder prototype

VTT X-ray collimator


MANUFACTURING FACTORY (Mid-2013)

Reactor building’s dome (03-2013)

Polar Crane (03 -2013)

Primary pompHydraulic tests

(Q3 2012)

GMP motorsRPP RUC RUP REP (01-2013)


VERY RECENTS PICTURES (REACTOR DOMEAND INSTALLATION OF THE 800 TONS CRANE)


VERY RECENT PICTURES (29TH NOVEMBER 2013)


JHR Experimental JHR Experimental JHR Experimental JHR Experimental Capacities (with development Capacities (with development Capacities (with development Capacities (with development

of instrumentation)of instrumentation)of instrumentation)of instrumentation)


CALIPSO & MICA

For material testingunder high dpaand controlled

thermal gradient(250 – 450°C)

MADISONFor LWR fuel testing

under nominal conditions

ADELINEFor LWR fuel testing

under off-normal conditions

OCCITANEFor pressure vessel

steel testing

Large experimentalfeedback

from CEA OSIRIS MTR

Fuel power ramp tests(Isabelle loop)

Material under controlled stress(GRIZZLY sample holder)

Etc.

Building the JHR experimental capacities


A high performance facility,With test devices having a wide range of capacitiesAnd an IMPROVED INSTRUMENTATION

In-pile instrumentation has to be : Reliable, Accurate, Miniature, High temperature resistant, Corrosion resistant, Neutron / γγγγ “resistant” (dose > 1GGy/d and > 10dpa/y in MTR)

An instrumentation for an accurate control of the test parameters and for an « on-line » measurement of the studied phenomena

SOME EXEMPLES of recent developpments…..

French-Swedish Seminar on Future Nuclear Systems -K TH -3rd December 2013APRIL 30, 2010

New self-compensated magnetic sensors (LVDT – DG) have been developed in partnership with IFE (Norway) for online measurement of sample elongation and diameter profile during irradiation

Self-compensated LVDT

Traction bellows

Compression bellows

Sample

Self-compensated diameter gauge

Internal pressure

MELODIE device

EXAMPLES OF CEA’S RECENT DEVELOPMENTS IN REACTOR INSTRUMENTATION : MELODIE

Accuracy = 1µm

Self-compensated diameter gauge

MELODIE (designed in collaboration with VTT-Finland) Creep test with bi-axial loading experimental device (controlled

bi-axial load) and on-line bi-axial deformation measurement device (sample diameter and length)

in a “MICA” hosting system

� to be operational in 2014 in OSIRIS reactor


Fission Gas Release determination using acoustic m easurement

Online measurement of the molar mass of the gas inside the fuel rod (� fraction of released fission gas )

Cavity connected to the

fuel rod

Fuel rod

Acoustic sensor �� Operational in OSIRIS reactor since 2011(REMORA-3 experiment)

The sensor is implemented on pre-irradiated PWR fuel rods

Patented

M

RTv

γ=


Sub-miniature fission chambers

CF Ø 1,5mm / 4mm / 8 mm

CF Ø 1,5mm

�� Operational in MTR, ZPR, etc.

Patented

Ionisation chambers with fissile deposit, external diameter down to 1,5mm, with integrated cable

Developed and manufactured by CEA in Cadarache (U, Pu, Np, Am, Cm, Th deposits…)


JHR Operation RulesJHR Operation RulesJHR Operation RulesJHR Operation Rules

Secondee ProgramSecondee ProgramSecondee ProgramSecondee Program

VRVRVRVR----CEA AgreementCEA AgreementCEA AgreementCEA Agreement


Governing Board

CEA Nuclear Operator

Project leader

International Programme (4 years plan)

For Members of the Consortium and Non-members

Proprietary

Programs

Joint international Programs

&

Validation

OPERATING RULES OF JHR : AN INTERNATIONAL USERSFACILITY WORKING AS AN INTERNATIONAL USER FACILITY


ACCESS TO JHR EXPERIMENTAL CAPACITIES FOR NON-MEMBERS

Governing Board propose a part of the ROP (Referenc e Operation Plan) open to non-members for setting-up International R&D programs having access to the fu ll experimental capacities of JHR including PIE

The International Programs can be open to any insti tutes working on nuclear R&D for civil purposes

Funding support can come from various sources (Euro pean Commission, OECD, Hosting Country…)


JHR AS AN INTERNATIONAL FACILITY

Create international scientific networks Make available facilities and resources to affiliatesLead innovative joint programs with shared results Host international scientists/engineers Provide “hands on” nuclear education “in the field”


TOWARDS AN INTERNATIONAL FACILITY…JHR SECONDEE PROGRAM

Building an International User Facility around JHR: � A key Issue for future R&D in nuclear energy � Strong CEA intention to Welcome Scientists , Engineers for a limited period of time within

JHR team for various topics (Secondee ) � Linked to the « open » part of the Operating Mode of JHR (Joint Programs)� Link with ICERR-IAEA Initiative to support MS willing to go on Nuclear Energy via the

setting-up of a RR (a clear benefit for the Decisison makers)

Academic Training Commercial Training linked to

a « product »

ICERR for Nuclear Education

« in the field »

Member State

A long term relationship to learn Best Practices in: Material and Fuel Sciences,Nuclear Safety,Reactor Operation,Nuclear Technologies….


-30.00

-20.00

-10.00

0.00

10.00

20.00

30.00

200 300 400 500 600

Niveau(mm)

0.00

0.50

1.00

1.50

2.00

R_N

VG

(Sah

a-Z

uber

)

Mesures

Calculs CATHARE (DB+40%&Thom)

Apparition significative de la vapeur (NVG)modèle CATHARE(Saha-Zuber mod)

= redistribution du débit

Calculs CATHARE (DB+40%)

Echanges monophasiques Echanges ebullition nucléée sous-saturée

And what happens with Sweden ?

5 DÉCEMBRE 2013

In 2010: A collaboration agreement was signed betwe enthe Swedish Research Council (VR) and CEA

About 7 M€ to fund Swedish researchers on ASTRID and JHR projects

Within this agreement: The DEMO–JHR project (DEterministic MOdeling of the Jules Horowitz Reactor) led by Prof. Christophe Demazière consists in funding 3 PhD’s

-“Development of new procedures for the thermal-hydraulic simulation of JHR”

KTH - division of Reactor Technology – Henryk Anglart

-“Improvement of the nuclear safety CATHARE code based on thermal-hydraulic

experiments”

Chalmers – Division of Nuclear Engineering – Paolo Vinai

-“Propagation of uncertainties in depletion calculations for the JHR”

Chalmers – Division of Nuclear Engineering – Paolo Vinai

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CEA-VR(SRC) KICK-OFF SEMINAR(20TH-21ST NOVEMBER 2013-CADARACHE)

5 décembre 2013

| PAGE 33


TO SUMMARIZE…

Experiment in MTRs will remain essential in the nex t decades in support for simulation and in support for the development and the qualificatio n of nuclear fuel and structural materials

JHR, in the prolongation of OSIRIS, will be a major facility for the European and International community, considering its hosting capacities and its high characteristics about neutron fluxes and spectra

Its experimental capacity is innovating and with a large range of operating conditions (test loops, FP laboratory, NDE equipment,..)

The on-line measurements are essential for the control of the experimental c onditions (it guaranties the quality of the experiments).

The complementarity of JHR with the hot labs dedicated to fuel and material examinations (LECA – LECI) will make possible to propose, to the scientific international community, a high level of expertise and competences in the fields of simulation, in-pile and out-of-pil e experiments, and sample characterizations.

European and International Collaboration on JHR is already and will be a major topic for this User Facility

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