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16th IGORR Conference-IAEA TM Meeting | PAGE 1
The Jules Horowitz Research Reactor
A new high performance Material Testing Reactor
working as an International User Facility
Gilles BIGNAN; Xavier BRAVO ; Jerome ESTRADE
French Atomic and Alternatives Energies Commission (CEA)
(Cadarache and Saclay Centre) Corresponding author: [email protected]
R&D in support to nuclear Industry
Safety and Plant life time management (ageing & new plants)
Fuel behavior validation in incidental and accidental situation
Assess innovations and related safety for future NPPs (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
Training of new generations Maintaining a national expertise staff and credibility for public acceptance Assessing safety requirements evolution and international regulation harmonisation
JHR 3 MAIN OBJECTIVES
JHR design and performances
JHR general design : a 100MWth pool type light water
MTR optimized for fuel and material testing
| PAGE 4
BR : Φ 37m H 45m
BAN : 51x47m H 35m
Pool : Φ 7m H 12m
About 200 aseismic pads Core Designed for UMo-Al fuel
Start-up with U3Si2-Al fuel
70 MWth / 100 MWth
25 to 30 days cycle length
6-7 days shutdown
Rooms dedicated to
reactor operation (heat exchangers, primary
pumps, safety systems,…)
Rooms dedicated to
reactor operation (control room, hot
workshop, labs,…)
Remind : Hosting experimental systems
(dedicated to LWR fuel testing)
19 NOVEMBRE 2014 | PAGE 5
MADISON
For fuel testing under nominal
conditions
ADELINE
For fuel testing under
off-normal conditions
reference possible evolution
Power transient,
post clad failure fuel behavior,
Lift-off experiment…
LORELEI fuel testing under accidental conditions
(LOCA)
• Source Term
(FP releases)
•Rod thermal-
mechanical
behaviour Ballooning and clad
burst (fuel relocation)
Corrosion at high
temperature
Quenching and post-
quench behaviour
EDF
Support
CEA
Support IAEC In-
Kind
19 NOVEMBRE 2014 | PAGE 6
- Irradiated material behaviour tensile tests, resilience test (Charpy),
crack propagation tests …..
-Behaviour of Thermal
affected zones
CLOE Corrosion loop
for “Zr alloy Corrosion” and
“Irradiation Assisted Stress
Corrosion Cracking”
OCCITANE
For pressure vessel steel testing
Four 2
Four 4
Four 6
Four 5
Four 3
Four 1
Four 2
Four 4
Four 6
Four 5
Four 3
Four 1
CALIPSO, MICA
For material testing
under high dpa
and accurate
temperature control
(+ mechanical loading)
specimen for µ structure evolution, tensile test ;
for 1 or 2 D creep tests ; for bending tests (stress
releiving experiments) ;…
Remind : Hosting experimental systems (dedicated to LWR material testing)
DAE
In-Kind
CEA
Support
CEA
Support
Hosting experimental systems under conceptual design
and/or extra-supply experimental loop
(example IGCAR RISHI Na Loop)
| PAGE 7
Transmutation
studies
CALIPSO adapted to
SFR fuel and material
Normal=> in core
Off normal => in reflector (SCK possible
contribution)
High temp.material irradiation (600-1000°C)
Large capacityMICA (material irrad) adapted to 1000°C gas
conditions (Phaeton type – Osiris technology)
Electrical heater
EM Pump
Exp. Samples
Heat exchanger
Neu
tro
n f
lux
Wa
ter f
low
NaK guide tube
Electrical heater
EM Pump
Exp. Samples
Heat exchanger
Neu
tro
n f
lux
Wa
ter f
low
NaK guide tube
LWR : Adeline « FP » ; Adeline “power to melt”
LWR severe accident studies
GFR : fuel irradiation (normal and off-normal conditions)
Fuel characterization : basic properties under irradiation
(thermal diffusivity, thermal creep,..)
Other topics
minicomposite
Containment
by-pass
Expected Experimental He Content and HM Depletion at EOL
0.000%
1.000%
2.000%
3.000%
4.000%
5.000%
6.000%
7.000%
8.000%
9.000%
10.000%
0.00E+00 2.00E-01 4.00E-01 6.00E-01 8.00E-01 1.00E+00 1.20E+00 1.40E+00
mg He/g initial HM
% o
f H
M d
ep
leti
on
Diamino 15% Am 200efpd
Diamino 7.5% Am 400efpd
SFR blanket 15% Am 1700efpd
SFR blanket 15% Am 3600 efpd
JHR 15% Am max flux 270efpd
JHR 15% Am max flux 520efpd
JHR 15% Am 10% enr 10% flux 270 efpd
JHR 15% Am 10% enr 10% flux 520 efpd
JHR 15% Am depl 33% flux 270efpd
JHR 15% Am depl 33% flux 520efpd
JHR 15% Am depl 10% flux 270efpd
JHR 15% Am depl 10% flux 520efpd
SFR reference
JHR baseline
expected DIAMINO results
15% and 7.5% Am
JHR capacities for LWR severe accident studies:
High temperature technology (core degradation studies) and FP
experimentation can be adapted to JHR environment
Depending on the objectives, the «severe accident test» will switch:
- From an experiment among others (JHR = multi-users facilty)
-To a dedicated irradiation (core power adapted to this specific test)
-Or to a dedicated facility (due to the pre and post test operations)
JHR OPERATING RULES
JHR CONSORTIUM & GOVERNING BOARD
JHR Consortium current partnership: Research centers & Industrial
companies
IAEC
Associated Partnership: NNL is the UK representative to JHR
UK/CEA agreement – March 2013
19/03/2007 Signature of the JHR
consortium
In some cases, the organization (member of the JHR consortium) is itself
the representative of a national consortium which gathers organizations
among industry, R&D organizations, TSO, or safety authority
JHR consortium gathers organizations which
take part financially in the construction of JHR
(1 representative / organization)
Governing Board
(JHR Consortium Members)
CEA
(Nuclear Operator)
JHR Reference Operation Plan (4 years plan)
For Members of the Consortium and Non-Members
Proprietary Programs Joint international
Programs(open to non-
members)
&
JHR : an International Users Facility
working as an International Center of Excellence
Nuclear safety ; Technical and
Economical performance (operation cost)
Project leader appointment
Validation of operation plan, business
strategy, economy of the project
Operation plan fulfilment
programs definition (preparation of next
Operation Plan with users) Project leader
Status of JHR project Fall 2014
GENERAL NUCLEAR UNIT OVERVIEW
JHR Presentation n° 2 - CEA-Cadarache - 08/04/2014
Levée 16
Levée 15b
REACTOR POOL
October 2012
November 12th 2013
Integration of first element of the structural support of liner
JHR Presentation n° 2 - CEA-Cadarache - 08/04/2014 | PAGE 13
INSTALLATION OF THE DOME
DECEMBER 2013
7th Governing Board / CEA-Cadarache24/06/2014 | PAGE 14
| PAGE 15
April 2014
| PAGE 16
Recent Pictures (August-September 2014)
JHR PROJECT SCHEDULE UPDATE MID- 2014
| PAGE 17
2017 2018 20192011 2012 2013 2014 2015 2016
Cold and core tests
Pool liner installation
Reactor block installation
HVAC + fluid circuits + electrical system + reactor block studies & supply
Nuclear Unit construction (Civil works)
First criticality
HVAC + fluid circuits + electrical system installation
Preparing JHR International Community:
- The yearly seminar - The 3 Working Groups
- IAEA ICERR - Secondee Program
LAST APRIL 2014 JHR SCIENTIFIC AND TECHNICAL SEMINAR
ON EXPERIMENTAL CAPACITIES (CADARACHE)
About 80 participants to share and discuss progress on the latest developments
on JHR experimental capacity
This 4th edition was open
to some non-members
(presence of Poland-NCBJ- and
Italy-Bologna University)
Opportunity for some
Consortium Members to present
The latest development of their
in-kind contribution:
- IAEC: LORELEI Loop for LOCA studies
- DAE: CLOE Loop for Corrosion studies
- Tecnatom: Simulator « Ex-simu »
- VTT : Non-Destructive Equipments
First Feedback from the JHR
Working Groups:
- Fuel R&D issues
- Material R&D issues
- Technology issues for experimental devices
MATERIAL WORKING GROUP
EXAMPLE OF POTENTIAL TOPICS OF INTEREST
Gen II / III
| PAGE 21
Topic Objective Material Instrumentation
Flux
(n.cm-2.s-1)
Fluence
(n.cm-2) / dpa Temp. (°C) Device
Reactor
Pressure
Vessel
Dose accumulation Low alloyed
steels
Loading
T control during
shutdown
1011 – 1013 < 2.1020
0,3 dpa 240 – 320
OCCITANE (not available at the start-
up of JHR)
Internals
Dose accumulation
Stainless
steels, Ni-
based alloys
Loading,
displacement
measurements
T control during
shutdown
1012 – 1014 10 – 80 dpa 320 – 390
OCCITANE (not available at the start-
up of JHR)
Environment effect CLOE
Mechanical testing MICA / CALIPSO
Cladding
Mechanical
properties Zr-alloys,
Austenitic
steels
Loading,
displacement < 3. 1014
< 400°C MICA / CALIPSO
(MELODIE)
Accident tolerance LORELEI
JHR Experimental devices specifications in accordance
with all the needs expressed
JHR toward an International
User-Facility : links with the ICERR –IAEA initiative
(International CEnter based on Research Reactors)
Cf A.Borio di Tigliole presentation
(this conference)
TOWARDS AN ICERR…CEA PROPOSAL:
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….
POTENTIAL SCIENTIFIC AND TECHNICAL SKILLS TO BE
ADDRESS VIA ICERR WITHIN JHR AND ITS ANCILLARY FACILITIES
Reactor
Operation
Safety Culture
Radioprotection Core Physics
Waste Management
Thermohydraulic
Safety studies Fuel Issues
Nuclear Technology
Material Issues
| PAGE 26
Recent Pictures (August-September 2014)
