HAL Id: hal-02416242
https://hal.archives-ouvertes.fr/hal-02416242
Submitted on 17 Dec 2019
HAL is a multi-disciplinary open access
archive for the deposit and dissemination of sci-entific research documents, whether they are pub-lished or not. The documents may come from teaching and research institutions in France or abroad, or from public or private research centers.
L’archive ouverte pluridisciplinaire HAL, est destinée au dépôt et à la diffusion de documents scientifiques de niveau recherche, publiés ou non, émanant des établissements d’enseignement et de recherche français ou étrangers, des laboratoires publics ou privés.
Future MTR capabilities Jules Horowitz
ReactoretIn-core instrumentation for MTR experiments
J.-F. Villard, G. Bignan
To cite this version:
J.-F. Villard, G. Bignan. Future MTR capabilities Jules Horowitz ReactoretIn-core instrumentation for MTR experiments. ICTP/IAEA Workshop “Research Reactors for Development of Materials and Fuels for Innovative Nuclear Energy Systems”, Nov 2017, Trieste, Italy. �hal-02416242�
Future MTR capabilities :
Jules Horowitz Reactor
| PAGE 1
Jean-François VILLARD, Gilles BIGNAN
French alternative energies and atomic energy commission Nuclear Energy Division – Reactor Studies Department Cadarache – F-13108 St Paul Lez Durance, France
Joint ICTP/IAEA Workshop “Research Reactors for Development of Materials and Fuels for Innovative Nuclear Energy Systems”
Future MTR capabilities : Jules Horowitz Reactor
Summary
1. Context and objectives of the JHR 2. General figures of the JHR
3. Experimental capabilities of the JHR 4. JHR consortium and collaborations 5. Status of the reactor construction
1. Context and objectives of the JHR
6 NOVEMBRE 2017 | PAGE 3
1. Context and objectives of the JHR
PAGE 4
In-pile testing in support of the nuclear Industry
Just for France, 58 NPPs means more than 10 000 fuel assemblies under irradiation at a time…
The fuel has to be carefully designed, with enough Safety Analysis
Design Margins
+ new fuel managements + new LWR standards…
In-pile data required !
need to generate additional margins
1. Improve Modeling, Calculation tools and Testing 2. Improve Safety Analysis design Methods
1. Context and objectives of the JHR
PAGE 5
The Key-Role of Material Testing Reactors for Fuel and Material qualification under irradiation
BASIS RESEARCH & NUMERICAL SIMULATION SINGLE EFFECT EXPERIMENTS POST IRRADIATION EXAMINATIONS MANUFACTURING REFABRICATION CHARACTERIZATION BEHAVIOUR UNDER IRRADIATION
Material Test Reactor
Hot Lab.
EXPERIMENTAL DATA EXPERTISE
Hot lab. for PIE
CODES Validation QUALIFICATION Documents CEA DESIGN
MTRs in France
1. Context and objectives of the JHR
PAGE 6 OSIRIS Shutdown 2015 SILOE Shutdown 1997 PHENIX Shutdown 2010
1. 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
2. Radio-isotopes supply for medical application
99Mo production
JHR will supply 25% of the European demand (today about 8 millions protocols/year)
+ Up to 50% upon specific request
3. A key tool to support expertise
Training new generations (JHR simulator, secondees program) Maintaining a national expertise staff and credibility for public acceptance
Assessing safety requirements evolution and international regulation harmonization
Jules Horowitz Reactor
1. Context and objectives of the JHR
PAGE 7
2. General figures of the JHR
6 NOVEMBRE 2017 | PAGE 8
JHR: a modern 100 MWth pool-type light water MTR optimized for fuel and material testing
2. General figures of the JHR
General layout of the JHR site Warehouse and cold workshop Offices Cooling systems Changing rooms + power supply Reactor pool (DD, NDE) Experimental rooms
Storage pools (NDE)
Control room Hot cells
(NDE + handling)
Reactor
Building Laboratories
2. General figures of the JHR
PAGE 10
Nuclear Auxiliary Building
About 200 aseismic pads
FP laboratory
dedicated to on-line FP measurement
Cubicle ; Control of Thy conditions and water treatment piping penetration Connection lines Reactor vessel Test device
I&C rooms for loop + test
device
Core
2. General figures of the JHR
PAGE 11
Thermal neutron flux
The core is under moderated:
High fast neutron flux in the core
High thermal neutron flux in the reflector
2. General figures of the JHR
PAGE 12
In reflector Up to 5.5 1014n/cm².s
~20 fixed positions
(100mm ; 1 position 200mm)
and 6 displacement systems Fuel studies: up to 600 W/cm with a 1% 235U PWR rod In core Up to 5.5 1014n/cm².s > 1 MeV Up to 1015n/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 3 Si 2 - Al fuel
70 MWth / 100 MWth 25 to 30 days cycle length
6 - 7 days shutdown 1 /L e th a rg y Material ageing (up to 16 dpa/y)
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/Le thargy Position 103 Position 101 Position C313 SFR core reference 1,E+08 1,E+09 1,E+10 1,E+11 1,E+12 1,E+13 1,E+14
1,0E-09 1,0E-08 1,0E-07 1,0E-06 1,0E-05 1,0E-04 1,0E-03 1,0E-02 1,0E-01 1,0E+00 1,0E+01 1,0E+02 Energie (MeV) F lu x p ar u n ité d e léth ar g ie (n /cm 2 /s) T12 à 0 mm T12 à 50 mm T12 à 100 mm T12 à 150 mm T12 à 200 mm SàD T12 0,7 3,0 1,0 0,4 0,1 0,1 2,5 4,4 2,0 0,7 0,3 2,6 2,6 2,3 2,1 1,9 2,0 0,7 1,2 0,7 0,4 0,2 0,2 P612 T12 T12 à 50 mm T12 à 100 mm T12 à 150 mm T12 à 200 mm Valeurs au centre du dispositif
sauf RS Pr ésence d'un e lame d'eau 0,74 1,04 0,73 0,87 0,81 0,21 2,55 3,35 2,63 2,68 3,29 0,86 2,64 3,13 2,74 2,73 2,63 2,06 0,75 0,96 0,74 0,77 0,78 0,43 H 2O H 2O lourde Z rH 2 C aH 2 H2 H 2 c onc ent ré F> 0 ,1 MeV (1E 1 3 n /cm ²/s) F> 1 MeV (1E 1 2 n /cm ²/s) Rap p o rt d e sp e ctre RS (F > 0 ,1 / F> 1 ) E ch a u ff e m e n t g a m a (W /g ) V a leu rs au ce n tre d u d ispo sitif sa u f RS (+ 50 m m d'ac ier) (+ 37 ,5 m m d'ac ier) (+ 35 m m d'ac ier) (+ 37 ,5 m m 12
In reflector (moving system) In core and in reflector
Fast flux Thermal flux
A large range of neutron fluxes and spectra
(and possible adaptation with « neutron filters »)
2. General figures of the JHR
Neutron spectra
3. Experimental capabilities of the JHR
6 NOVEMBRE 2017 | PAGE 14
6 NOVEMBRE 2017
PAGE 15 - 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) ;…
Hosting experimental systems (dedicated to LWR material testing)
Hosting experimental systems (dedicated to LWR fuel testing)
PAGE 16
MADISON
For fuel testing under nominal conditions
ADELINE
For fuel testing under off-normal conditions
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
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 capacity
MICA (material irrad) adapted to 1000°C gas
conditions (Phaeton type – Osiris technology)
Electrical heater EM Pump Exp. Samples Heat exchanger Neutron fl ux Wa te r f lo w
NaK guide tube
Electrical heater EM Pump Exp. Samples Heat exchanger Neutron fl ux Wa te r f lo w
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+002.00E-014.00E-016.00E-018.00E-011.00E+001.20E+001.40E+00
mg He/g initial HM % of HM deplet ion 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
Other possible hosting experimental systems (conceptual studies)
3. Experimental capabilities of the JHR
PAGE 18 Gamma and X-Ray
tomography systems Multipurpose test benches
LINAC (X)
-detector Shielding
XR-detector
Tunablefront collimator Device
Side cutaway
Pool bank fixing
Penetration X-table Y-table Bench Z-table XR-collimator
View from the core
Coupled Gamma &X-ray bench
Coupled X-ray & bench in storage pool Neutron imaging system
in reactor pool Coupled X-ray & bench in reactor pool
Test device
examination in pools
Sample examination in hot cells
Initial checks of the experimental loading Adjustment of the experimental protocol On-site NDE tests after the irradiation phase
Neutron Imaging System
Non Destructive Examination (NDE) Benches
4. JHR consortium and collaborations
6 NOVEMBRE 2017 | PAGE 19
4. JHR consortium and collaborations
JHR Consortium : economical model for investment & operation CEA = Owner & nuclear operator with all liabilities
JHR Consortium Members own Guaranteed Access Rights (in proportion of their financial commitment to the construction)
A Member can use totally or partly his access rights for implementing
proprietary programs with full property of results and/or for participating to
the Joint International Programs open to non-members
Open to new member entrance until JHR completion
JHR Consortium current partnership: Research centers & Industrial companies
IAEC
Associated Partnership: JAEA
Strong CEA intention to welcome Junior and/or Senior Scientists, Nuclear Engineers, Operators, Safety Managers… within JHR teams for various
topics (R&D programs, Hands-on training on equipment…)
Since CEA designation in September 2015, 6 Member States from the IAEA have signed an Agreement with CEA
Objectives of the CEA-ICERR (IAEA Terms of Ref):
Create international scientific networks
Make available CEA facilities and experience to affiliates
Lead innovative joint programs with shared results Enhance utilization of Research Reactors
Host international scientists / engineers (visiting scientists, operators…)
Provide “hands on” nuclear education “in the field”
THE JHR AND ANCILLARY FACILITIES AS AN “ICERR”
4. JHR consortium and collaborations
5. Status of the reactor construction
6 NOVEMBRE 2017 | PAGE 22
Civil work of Reactor Building and Auxiliary Unit Building
nearly completed
Delivery of Hot Cells end of 2016 (Czech partners)
Preparation for pool liner setting-up
5. Status of the reactor construction
December 2016
March 2017
5. Status of the reactor construction
March 2017 : NUCLEAR UNIT CLOSURE
PAGE 25
Horse saddle flange
Last welding on the vessel Electron beam welding
Rack for fuel elements Main water box with
primary system connection
Heat Exchangers (Spanish partner)
Core components
JHR Fuel qualification
(EVITA Program performed in BR2 reactor)
5. Status of the reactor construction
Development and experimental validation of a new
calculation scheme for JHR
5. Status of the reactor construction
PAGE 27
AMMON program performed in EOLE reactor (2010-2013) :
provided relevant experimental data for the qualification of the main JHR
safety and design parameters
AMMON « reference » configuration 1 0 2 1 0 3 1 0 4 1 0 5 1 0 6 1 0 1 0 0 1 11 12 13 14 15 16
Future MTR capabilities : Jules Horowitz Reactor
General conclusion
1. Material Testing Reactors remains key-tools in R&D support for
nuclear power industry
2. Research Reactors are now more “costly machines” than in the
past…
3. Considering the increasing complexity of the experiments (due to
enhanced requirements from simulation) the use of international platform (as will be JHR) is recommended
4. Innovative in-core instrumentation is a key for the quality and
attractiveness of future MTR experimental programs, together with
Post-Irradiation Analysis capabilities
Nuclear Energy Division Reactor Studies Department Experimental Physics Section
Instrumentation Sensors and Dosimetry Laboratory French alternative energies and atomic energy commission
Cadarache | F-13108 Saint-Paul-lez-Durance | France
T. +33 (0)4 42 25 79 62 | F. +33 (0)4 42 25 78 76
Etablissement public à caractère industriel et commercial RCS Paris B 775 685 019
6 NOVEMBRE 2017 | PAGE 37
