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Sodium Fast Reactor
Philippe DufourSFR SSC Chair
2015 GIF symposiumSession II19 May 2015
Slide 2Tokyo, May 2015
The SFR system was identified during the Generation IV Technology Roadmap as a promising technology to perform the actinide management mission and if enhanced economics for the system could be realized, also the electricity and heat production missions. The main characteristics of the SFR that make it especially suitable for the actinide management mission are:
• Consumption of transuranics in a closed fuel cycle, thus reducing the radiotoxicity and heat load which facilitates waste disposal and geologic isolation.
• Enhanced utilization of uranium resources through efficient management of fissile materials and multi-recycle.
• High level of safety achieved through inherent and passive means that accommodate transients and bounding events with significant safety margins.
Slide 3Tokyo, May 2015
System Research PlanGeneration IV Nuclear Energy Systems
System Research Planfor the Sodium-cooled Fast Reactor
Issued by theGeneration IV International ForumSFR System Steering Committee
Preparing Today for Tomorrow’s Energy Needs
Development Targets and Design RequirementsSFR R&D Projects• System Integration and Assessment (SIA)• Safety and Operations• Advanced Fuel• Component Design and Balance of Plant• Global Actinide Cycle International
Demonstration (GACID)
SFR Design Concepts• Loop Option (JSFR Design Track)• Pool Option (KALIMER-600 & ESFR Design
Tracks)• Small Modular Option (SMFR Design Track)
SRP was updated and released in July 2013
Revision 2
July 12, 2013
Slide 4Tokyo, May 2015
EUR FRA JPN PRC ROK RUF USA
SFR System Arrangement(Signed - 15 Feb 2006)
X X X X X X X
SFR AF PA(Signed - 21 Mar 2007)
X X X P X P X
SFR GACID PA(Signed - Sept 2007)
X X X
SFR CDBOP PA(Signed - 11 Oct 2007)
P X X 2016 X 2016 X
SFR SO PA(Signed - 11 June 2009,Resigned – 15 Nov 2012)
X X X X X X X
SFR SIA PA(Signed - 22 Oct 2014)
X X X X X X X
Status of SFR Arrangements
X=Signatory, D=Under Discussion, P=In Progress
Slide 5Tokyo, May 2015
Gen IV SFR System Options and Design Tracks
Loop Pool Small Modular
KALIMERJSFR SMFR
IHXDHX
PHTS pump
Reactor core
Steam Generator
AHX Chimney
PDRC piping
In-vessel core catcher
IHTS piping
IHTS pump
IHXDHX
PHTS pump
Reactor core
Steam Generator
AHX Chimney
PDRC piping
In-vessel core catcher
IHTS piping
IHTS pump
12.03 m
3,186 gal.
PLAN VIEW OF THE CORE
PRIMARYCONTROL RODS
1m TRAVEL DISTANCEOF THE CONTROL RODS
(10'-8")
THERMALSHIELD
(29.5")0.75m
3.25m
Na-COHEAT EXCHANGER
7m
IHX
X-SECTION (FLATTENED FOR CLARITY)
(23')
(Ø 7.5' x 12.6' LONG)
IHX
2
SECTION A - A
Normal s odium level
Normal s odium level
Sodium faulted level
Pump offSodium Level
SODIUM DUMP TANKØ 2.5 m x 3.8 m LONG
CORE BARREL Ø266 / 268 cm(104.7" / 105.5")
SECONDARYCONTROL RODS
CONTROLRODS (7)
PUMPS (2)ON Ø 142.5" B.C.
PLAN VIEW OFIHX AND PUMPS IHX (2)
1.7m EACH2
DRACS (2)0.4m EACH2
Primary Vessel I.D.
Guard Vessel I.D.
Hot Pool
Cold Pool
PRIMARY VESSEL
(2" THICK)
3.5m(11'-8")
GUARD VESSEL(1" THICK)
1m(39.4")
3
TURBINE/GENERATORBUILDING
ELEVATOR
(Ø 25.5')Ø 7.7m
Na-AirHEAT EXCHANGER (2)
CONTROLBUILDING
0 1 2 3 10METERS4 5
5.08m [16.7FT]
4.57m [15FT]
7m [23FT]
1.89m
[6.2FT]
12.72m [41.7FT]
14.76m [48.4FT]
1.93m [6.3FT]
.61m [2FT]
2.29m [7.5FT]
EXHAUST TO VENT STACK
ESFR
BN-1200 will be presented by Russia as new Gen-IV SFR design track for the next SIA meeting
Slide 6Tokyo, May 2015
System Integration & Assessment Project
Slide 7Tokyo, May 2015
System Integration & Assessment ProjectObjectives
– Integration of the results of R&D Projects– Performance of design and safety studies– Assessment of the SFR System against the goals and criteria set
out in the Gen IV Technology Roadmap
Integration RoleSpecific tasks have been developed and refined– Identify Generation-IV SFR Options
» General system options» Specific design tracks» Contributed trade studies
– Maintain comprehensive list of R&D needs– Review Generation-IV SFR Technical Projects– Unlike the technical Projects, based on synthesis o f results
produced by other Projects
Slide 8Tokyo, May 2015
Safety & Operation Project
Slide 9Tokyo, May 2015
Project Objectives• Analyses and experiments that support safety approa ches and
validate specific safety features• Development and validation of computational tools u seful for such
studies• Acquisition of reactor operation technology, as det ermined largely
from experience and testing in operating SFR plants
S&O Project
France (CEA)
Japan (JAEA)
Korea (KAERI)
US (USDOE)
Members
EURATOM (JRC)
China (CIAE)
RF (Rosatom )
Slide 10Tokyo, May 2015
T°C
T°C
T°C
Zone 1
Zone 2
Zone 3
Zone 4Zone 5
DHR modeling through the PV
Very severe conditions assumed. Blackout with loss of all in vessel DHRS.
A model including convection, conduction and radiat ion was developed
Sensitivity calculations on SS emissivity were perf ormed
Need of fill the space between the main and safety vessels with sodium to reach acceptable temperatures.
TMV°iTMV°eTSV°iTSV°eTRV°
PTh
MVSVRV
P1P2
H
0
T°C
Slide 11Tokyo, May 2015
A report on analytical methods to simulate phenomen a in self-leveling behavior of the debris bed
Development of the debris bed self-leveling model f or IVR confirmation
0sec
30sec
60sec
Proposed model Experiment
Self-leveling behaviorof debris bed
at relocation phase
Slide 12Tokyo, May 2015
SAS4A severe accident model development and prelimi nary analysis
-0.04
-0.02
0.00
0.02
0.04
0.06
0.08
0.10
0 10 20 30
rea
ctiv
ity
($)
time (s)
Net reactivity
1.0
1.1
1.2
1.3
1.4
1.5
0 10 20 30
no
rma
lize
d p
ow
er
time (s)
Normalized power
z(m
)
0 0.002 00
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z(m
)
0 0.0020
0.2
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r(m)
z(m
)
0 0.002 0.004 0.0060
0.2
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0.8 T(K)
1000980960940920900880860840820800780760740720
z(m
)
0 0.002 0.0040
0.2
0.4
0.6
0.8 Margin(K)
550500450400350300250200150100500
-50-100
U, Zr weight fraction Margin to melt
Map of molten fuel Temperature
Slide 13Tokyo, May 2015
Advanced Fuel Project
Slide 14Tokyo, May 2015
Advanced Fuel Project• Objective
– Selection of high burn-up MA bearing fuel(s), cladd ing and wrapper withstanding high neutron doses and tempera tures
• Candidates:– Driver fuels: Oxide, Metal, Nitride & Carbide (sinc e 2008)
Inert Matrix fuels & MA Bearing Blankets (since 200 9)– Core materials: Ferritic/Martensitic & ODS steels
• Scope– Fabrication– Behavior under irradiation
• Signatories (country – implementing agent): France - CEA, USA -DOE, EURATOM - JRC/ITU, Japan - JAEA, Korea -KAERI
Slide 15Tokyo, May 2015
Progress / carbide & nitride fuels Carbothermal reduction process revisited -> Identification of reaction schemes & intermediate
species (Handschuh et al, 2010, Conf. Pu future)
Am bearing fuels synthesis
Fuel element advanced pre-design -> plate
(Carvajal et al., JNM, 2014, accepted)(Rimpault et al., proceedings GLOBAL 2009)
Non Destructive Examinations of a (U 0.5Pu0.25Am0.15Np0.10)N fuel rodlet, Na bonded,
irradiated in ATR (17at%, 270W.cm-1) within the ser ies AFC-1 -> satisfactory results
consistent with predicted behavior
Slide 16Tokyo, May 2015
Progress / metal fuels
• Fuel slug fabrication:– gravity-casting & pressurized injection casting (Lee et al., proceedings FR-13):
» U-Zr-Mn & U-10Zr-RE-Mn (RE: 1-10%, Mn :0 & 5%)
» retention of Mn (Am surrogate)
– Implementation of the Glovebox Advanced Casting System at INL
->Pu & Am bearing fuels, 3 slugs/batch, Φ: 4,5mm & 250mm long
with a re-usable mold (Fielding et al., FR-13)
• Irradiations:
– SMIRP-1: PIE on UZr & UCeZr slugs irradiated (2.7at%) in HANARO (Lee et al., FR13)
-> satisfactory behavior & Cr layer at fuel/cladding interface to prevent FFCI performed well, despite some cracks in the Cr layer
Slide 17Tokyo, May 2015
Progress / core materials
• F/M & ODS steels– HT9 cladding tube manufacturing processes
-> melting, forging, machining, hot-extrudingdrawing & pilgering, annealings …
– Welding : Electro-Magnetic Pulse Technology -> joining of tubing and end caps for T91
and ODS
– Metallic Fuel / Cladding Chemical Interaction mitigation: » investigation of cladding liner materials & liner deposition processes
– barriers : Cr, V, Cr2O3, …– methods : CVD, electroplating, …
– ODS fuel pin irradiation in JOYO under preparation
Slide 18Tokyo, May 2015
Component Design & BOP Project
Slide 19Tokyo, May 2015
CD & BOP Project Subjects for 2012 -2016
(1) In-Service Inspection & Instrumentation (ISI) t echnology• Ultrasonic inspection in sodium using different app roaches and technologies, codes
and standards (CEA, Euratom , JAEA, KAERI) (2) Repair experience
• Phénix, Monju, (CEA, JAEA)
(3) Leak Before Break (LBB) Assessment technology • Creep, fatigue, and creep-fatigue crack initiation & growth evaluation for Mod. 9Cr-1Mo
(Grade 91) steel, Na leak detection by laser spectr oscopy (JAEA, KAERI)
(4) Supercritical CO 2 Brayton Cycle Energy Conversion• S-CO2 compressor tests, S-CO 2 cycle demonstration tests, Compact heat exchanger
tests, Material oxidation tests in S-CO 2, Sodium -CO2 reaction tests, S-CO 2 SFR plant dynamic analyses and control strategy development, Computer code analysis, S-CO 2SFR design study, Validation of S-CO 2 plant dynamic analyses with S-CO 2 loop data, Sodium plugging tests (CEA, DOE, Euratom , JAEA, KAERI)
(5) Steam Generator design and associated safety & instrumentation (since 2011)• Na/water reaction, thermal-hydraulics, thermal perf ormance, DWT structural evaluation
and heat exchange performance, DWT-SG fabrication (CEA, JAEA, KAERI)
Slide 20Tokyo, May 2015
study of the supercritical CO 2 cycle
S-CO2 Brayton Cycle Energy Conversion
� CFD simulations of the small scale S-CO 2 compressor have shown good agreement with the experiment data
� Calculations were carried out with the ANL Plant Dy namics Code that performs system level transient analysis for S-CO2 cycles coupled to SAS4A/SASYS-1
Experiment data CFD simulation
Shaft speed, rpm 12000
Mass flow rate, kg/s 4.008 ± 0.007 4.008
Inlet temperature, oC 35.35 ± 0.5 35.35
Inlet pressure, bar 82.71 ± 0.20 82.71
Outlet temperature, oC 38.35 ± 0.5 38.98
Outlet pressure, bar 91.34 ± 0.20 91.31
-20%
0%
20%
40%
60%
80%
100%
120%
140%
160%
180%
0 400 800 1200 1600 2000 2400 2800 3200 3600 4000 4400 4800 5200
W,
FRA
CTIO
N O
F N
OM
INA
L G
EN
ER
ATO
R P
OW
ER
TIME, s
TURBINE AND COMPRESSORS WORK AND GENERATOR OUTPUT
W_Turb
W_Comp1
W_Comp2
W_gen
W_grid
0.0
0.2
0.4
0.6
0.8
1.0
1.2
0 400 800 1200 1600 2000 2400 2800 3200 3600 4000 4400 4800 5200
NO
RM
ALIZ
ED
PO
WER
OR
FLO
W
TIME, s
CORE POWER AND FLOW
POWER DECAY POWER PEAK CHANNEL FLOW
300
350
400
450
500
550
600
650
700
750
0 400 800 1200 1600 2000 2400 2800 3200 3600 4000 4400 4800 5200
TEM
PER
AT
UR
E,
oC
TIME, s
PEAK CORE TEMPERATURES
PEAK FUEL PEAK CLAD
PEAK COOLANT INLET
Slide 21Tokyo, May 2015
S-CO2 Brayton Cycle Energy ConversionCorrosion behavior of metallic materials in SC-CO 2
� Fruitfull collaboration between CEA and JAEA for more comprehensive understanding of corrosion mechanisms in SC-CO 2 (2012-2014).
� More than 350 corrodes samples, 11 steel grades, 5 temperatures (400 to 600C), up to 8000h exposure.
JAEA facility CEA facility
� Fast oxidation and carburization of 9-12Cr steels : s uccessful modeling of oxide growth rate and carburization rate.
� Much slower oxide growth (more than 100 times slowe r than 9-12Cr) and almost no carburization of 18-25Cr steels. Increasing %Cr d ecreases the degradation of the steel.
� No strong influence of CO 2 pressure on the corrosion behavior was observed.� At T > 400C, the use of austenitic steels are recom mended.
Slide 22Tokyo, May 2015
S-CO2 Brayton Cycle Energy ConversionPreparation of a Sodium -CO2 interaction test facility
�The fabrication of test facility for wastage and pl ugging issues is supposed to be finished by Mar. 2014 and main experiments wi ll be carried out in FY2014.- Wastage test : Damage propagation on the pressure b oundary in Na-CO 2 HXs - Plugging test : Channel plugging in Na-CO 2 HXs
CO2 injection with
controllable flowrate
Lchannel (< 1.0 m)
Test section schematic:
Plugging test channel
Sodium flow
A-A’
<Plugging Test (Section II)>
<Wastage Test (Section I)>
< Impinging angle: 90 o >
< Impinging angle: 45 o >
< Construction of test loop (Photo of Mar. 3, 2014) >
Slide 23Tokyo, May 2015
Steam GeneratorsPreparation of a basic heat transfer test facility for Double Wall Tubes
and G91 tube inspection technology
- Combined SG tube inspection sensorRFECT + Magnetic sensor testing
- Preliminary test of magnetic sensor testing system has been carried out.
- Construction of a basic heat transfer test facility for DWT has been finished.
Basic heat transfer test facility for DWTBasic heat transfer test facility for DWTBasic heat transfer test facility for DWTBasic heat transfer test facility for DWT (5.3 x 4.6 x 11.8 m)
RFECT exciter coilRFECT exciter coilRFECT exciter coilRFECT exciter coil RFECT pickup coilRFECT pickup coilRFECT pickup coilRFECT pickup coil
Magnetic sensorMagnetic sensorMagnetic sensorMagnetic sensor
Magnetic sourceMagnetic sourceMagnetic sourceMagnetic source
Combined SG tube inspection sensor (design example)Combined SG tube inspection sensor (design example)Combined SG tube inspection sensor (design example)Combined SG tube inspection sensor (design example)
20%20%20%20% 40%40%40%40% 60%60%60%60%
Magnetic sensor testing system and preliminary test resultsMagnetic sensor testing system and preliminary test resultsMagnetic sensor testing system and preliminary test resultsMagnetic sensor testing system and preliminary test results
20%20%20%20% 40%40%40%40% 60%60%60%60%
Outer circum. notch
Outer groove
Slide 24Tokyo, May 2015
Steam GeneratorsTrial fabrication of main parts of double-walled-tu be steam generator
Dies
Double-wall-tube drawing process
(Double-walled tube, tube-sheet, tube to tube-sheet junction)
Tube and tube-sheet welding test
Welder
Welding zoneInner tube
Outer tube
Slide 25Tokyo, May 2015
Steam Generators
25
Sodium/water reaction control technology using nano -size particles in sodium
Sodium combustionNa/water reaction (Computer analysis)
� The technology is to reduce the chemical reactivity of liquid sodium using nano-particle.
� The sodium chemical reactivity can be suppressed by an atomic interaction between nano-particle and sodium atom.
Reaction jetHeat transfer tube
Slide 26Tokyo, May 2015
In-service InspectionRecent progress in under-sodium viewing technology with waveguide
sensor: Development and applicability verification of a rem ote inspection module
Remote Inspection Module (4 Ch. WG sensors)Remote Inspection Module (4 Ch. WG sensors)Remote Inspection Module (4 Ch. WG sensors)Remote Inspection Module (4 Ch. WG sensors)
10 m
Upper drivingUpper drivingUpper drivingUpper driving
devicedevicedevicedevice
LowerLowerLowerLowerguidingguidingguidingguidingstructurestructurestructurestructure
- Remote inspection module employing 4Ch. 10 m long waveguide sensors was developed for ISI of reactor internals in an SFR.
- Several verification tests were carried out and the applicability of the remote inspection module to ISI of reactor internals was successfully demonstrated.
ObstaclesObstaclesObstaclesObstaclesObstaclesObstaclesObstaclesObstacles
ObstaclesObstaclesObstaclesObstacles
Ranging inspection resultsRanging inspection resultsRanging inspection resultsRanging inspection results
Viewing inspection resultsViewing inspection resultsViewing inspection resultsViewing inspection results
Identification inspection resultsIdentification inspection resultsIdentification inspection resultsIdentification inspection results
Slide 27Tokyo, May 2015
In-service InspectionRecent Developments of Ultrasonic Sensors for NDE i n liquid sodium
� New TUSHT (High Temperature Ultrasonic Transducers) were manufactured and performance tests were realized� These sensors were immerged in sodium up to 600 °°°°C
� New multielement EMAT (Electromagnetic transducer) – 8 phased array
< TUHST tested on DOLMEN Na facility at CEA >
• Optimization of the sensor to limit the piezoelement crystalchemical reduction
• Potential use in SONAR for in sodium telemetryapplication
• Demonstration of operation at 180°C• Ability to deflect the wave direction• New design to optimise the sensor
(enhance deflection, size reduction of focal spot)
Slide 28Tokyo, May 2015
GACID Project
Slide 29Tokyo, May 2015
Overview of GACID Conceptual Scheme
MA raw material preparationMonju
Fuel pin fabri-cation
Irradiation test
MA-bearing MOX fuel pellets
�Objective: to demonstrate, using Joyo and Monju, that FR’s can transmute MA’s (Np/Am/Cm) and thereby reduce the concerns of HL radioactive wastes and proliferation risks.
�A phased approach in three steps.�Material properties and irradiation
behavior are also studied and investigated.
Step-1Np/Am pin irrad. test Joyo
Step-3Np/Am/Cmbundle irrad. test
Monju (Final Goal)
Test fuel fabrication
Step-2Np/Am/Cm pin irrad. test
Monju
Planning
MonjuJoyo�The Project is being conducted by
CEA, USDOE and JAEA as a GIF/SFR Project, covering the initial 5 years since Sep. 27, 2007.
GACID overall schedule
1
Slide 30Tokyo, May 2015
Summary
Slide 31Tokyo, May 2015
• System Research Plan has been updated in order to i ncorporate changes in Project Plans and design concepts
• Various collaborative activities are being conducte d in the areas of advanced fuels, transmutation of MAs, component des ign and BOP, and safety and operation within the SFR Technical R&D P roject Arrangements
• Procedures of resigning SFR Technical R&D Project A rrangements is under way
• Signing SFR SIA PA will permit to integrate and ass ess the results of R&D work conducted under SFR Technical R&D Project Arrangements
Slide 32Tokyo, May 2015
Thank youfor your attention !
Slide 33Tokyo, May 2015
Primary Roles of SIA Project and Relation to Techni cal Projects
Concept DeveloperConcept Developer
System Steering Committee
Technical PMBs (AF, GACID, CDBOP and SO)
SIA Project
Concept Developer
Entire set of R&Ds
Integrate R&D results
Design Concept Study
Self-assessment
(JSFR, ESFR, KALIMER, SMFR)
• Maintain and refine SFR system options in SRP
• Contribute trade studies in support of system specification
• Specify R&D needs in technical PMBs• Review PPs to ensure the needs are met
• Assess & Integrate R&D results
Contribution as BPI/Voluntary
SRPWP 1
WP 3
WP 2