Contents Presentation of the monograph Topographic Maps at ...
Contents of the presentation
description
Transcript of Contents of the presentation
![Page 1: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/1.jpg)
12008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Towards the development of Thermal-Hydraulic Models aimed
at the Auxiliary Systems Design in Nuclear Fusion Technology
1L. Batet, 2L. Sedano, 1C. Queraltó, 1E. Mas de les Valls, 1J.Fradera and 1F. Reventós
1Technical University of Catalonia2Association Euratom-Ciemat for Fusion
![Page 2: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/2.jpg)
22008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Contents of the presentation
• Introduction• Background and context• LM Breeding Blanket designs in EU• BB channels CFD modeling• Auxiliary Systems for BB• Auxiliary systems modeling• EU experimental facilities• Conclusions
![Page 3: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/3.jpg)
32008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Introduction
• As for Gen IV Programmes, the developments in Nuclear Fusion Technology (NFT) are today demanding advanced computational capabilities for simulation and modeling of thermal-hydraulics of liquid metal systems.
• Attending to its functional requirements (DEMO Fusion reactors are today functionally conceived), breeding blanket (and auxiliary systems) is probably the most complex component developed today by energy technology. It represents a key component/system in the way to fusion power production (DEMO).
Breeding Blanket modules are just behind the first-wall, facing plasma. They perform three challenging key functions:
• Coil shielding from plasma radiation• Heat recovery from neutron flux• Tritium breeding
![Page 4: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/4.jpg)
42008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Introduction
• EU plan to test HCLL and auxiliary systems as Test Blanket Module (TBM) in ITER. The development of predictive tools aimed to the simulation of the behavior and to the analysis of those systems and components will be a key issue to licensing and to take advantage of the results from ITER experimental programmes.
• As DEMO breeding blanket, EU is developing diverse liquid metal (Pb15.7Li)-based concepts:– Helium-Cooled Lithium-Lead (HCLL), – Dual-Coolant/Dual-Functional Helium/Lithium-Lead (DCLL), and– Self-Coolant Lithium-Lead Concepts (SCLL).
Water-coolant (WCLL) concept is developed at the French National Programme. A Spanish National Programme (TECNO_FUS) is starting in Spain for Dual-Coolant concept development.
![Page 5: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/5.jpg)
52008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Introduction
• The Thermal-Hydraulic Studies Group (THSG) of the Technical University of Catalonia (UPC), in collaboration with CIEMAT, is trying to reach computational simulation capabilities in relation with breeding blanket liquid metal auxiliary systems for EU ITER TBMs (ITER Test Blanket Modules) and beyond (design of auxiliaries for DEMO HCLL and advanced modular DCLL-like named DRM He/LiPb) .
• A system TH code, like RELAP5-3D, will allow the formulation of the main mass and energy balances.
• The detailed analysis capabilities of a CFD code (UPC is using OPENFOAM) will provide support to the modeling of tritium diffusion and permeation, form-losses evaluation, etc.
![Page 6: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/6.jpg)
62008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Background and context
• Currently foreseen fusion reactors relay on the D+T reaction, which implies achieving tritium self-sufficiency.
• While deuterium is abundant in nature (30g/m3 of water), tritium is not.
• For a 1000 MWe reactor, the mass of tritium needed is some 360 g/day (compare with the production of one CANDU reactor, close to 2 kg/year).
• The Breeding Blanket is the solution proposed to produce tritium inside the reactor facility.
MeV6.17nHeHH 10
42
31
21
![Page 7: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/7.jpg)
72008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Background and context
MeV
MeV
47.2nHHeLin
78.4HHeLin10
31
42
73
10
31
42
63
10
• Tritium can be produced from Lithium:
• Probability of first reaction is orders of magnitude larger than the second one.
• Natural lithium has 92.44 % 6Li: isotopic enrichment is needed.
• Neutron multiplier needed (Pb or Be) to achieve the necessary Tritium Breeding Ratio (TBR) of about 1.15
![Page 8: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/8.jpg)
82008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Background and context
• Tritium cycle is complex and tritium control is difficult. • Diffusive properties of hydrogen isotopes are very large
compared with other elements. Permeation is a key issue regarding tritium inventory.
• Inventory control is of utmost importance:– Environmental impact: authorized release (it will depend on the
chemical form of the emissions) 1g/year (27 Ci/day) in front a production of some hundreds of grams/day.
– Self-supplying guaranty (very small margin between the maximum achievable TBR and the TBR needed)
![Page 9: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/9.jpg)
92008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
• To demonstrate the tritium self-sufficiency capability, along with licensing requirements, a detailed study of tritium inventory in the channels of the breeding blanket is mandatory.
• Tritium analysis require an exact knowledge of the hydrodynamic profiles in the surface layers, which can only be obtained through CFD simulation.
• CFD codes should be validated under the BB working conditions.
• First full experiment for TBM will be ITER.
Background and context
![Page 10: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/10.jpg)
102008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Joaquín Sánchez
Test Blanket Module (TBM) : mock-up of a DEMO blanket in ITER test portTBM System : TBM + various associated systems in Tokamak & other buildings
CPS = Coolant Purification System, TWCS vault
HCS = (He) Coolant System, located in TWCS vault, connected with ITER heat rejection system
TES = Tritium Extraction System, located in Port Cell, connected Tritium building
EU ITER-Test Blanket Module
![Page 11: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/11.jpg)
112008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
► Structures: RAF/M Steel (HCLL,WCLL) and (DCLL) or SiCf/SiC(SCLL) ► Multiplier/Breeder: Eutectic Pb-Li ► Coolant: He at 8 MPa, 300/500°C (only) or with LiPb at ~460-480°C/650-700°C
► EUROFER He-cooled steel box, highly modular, radial He-cooling plates► T steel: 350°C/550°C► T interface (steel) < 520°C► LiPb velocity < 1 mm/s ► Need of T-perm. Barr.,
► 6Li 90%
► Water-cooled FM steel box, large banana shape modules, poloidal tubes► T steel: 350°C/550°C► T interface (steel) < 520°C► LiPb velocity ~ mm/s ► Need of T-perm. Barr.
► 6Li 90%
► EUROFER/ODS+ SiC/SiC flow channel inserts as el./th.Insulator►LLE breeder & coolant► T steel: 350°C/550°C►T interf. SiC/SiC< 700°C► LLE velocity ~0.1 m/s► 6Li 90%
Water-Cooled LLEblanket (WCLL)
Self-Cooled LL blanket (SCLL)
Helium-Cooled LLE blanket (HCLL)
► SiC/SiC large banana-like structures, ► LLE breeder & total coolant► T interface (SiC/SiC) < 700°C
► LiPb velocity ~ 1 m/s► 6Li 90%
Dual-Coolant LLEblanket (DCLL)
LM Breeding Blanket designs in EU
![Page 12: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/12.jpg)
122008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
• CIEMAT and UPC are dealing with HCLL (ITER TBM) and DRM (for DEMO)
LM Breeding Blanket designs in EU
Helium- Cooled Lithium-Lead ½ V port size
.
• In cooperation with ENEA and CEA, a PbLi database compiled.
J.Nuc.Mat: E.Mas de les Valls et al., Lead-lithium eutectic material database for nuclear fusion technology. 2008
![Page 13: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/13.jpg)
132008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
BB channels CFD modeling
• THSG (UPC) is developing a CFD tool (based on the open source OpenFOAM code) to simulate the complex phenomena occurring in the liquid BB modules channels, including HCLL and the Dual Coolant Concept.
• Steps to follow:– MHD implementation– Validation using cases with analytical solution– Preparation of the post-processing for tritium– Validation and analysis of numerical diffusion (DT~10-9 m2/s)– Temperature coupling – Validation (?)– Application to the BB modules
![Page 14: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/14.jpg)
142008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
BB channels CFD modeling
• To adapt and validate OpenFOAM it has been necessary to implement a suitable numerical algorithm to simulate the TBM working conditions, i.e. MHD advection coupled to the tritium diffusion/permeation under an intense magnetic field (high Hartmann, high Interaction Parameter) and large thermal loads (neutron radiation).
• The implemented MHD code has been satisfactorily validated.
• Future improvements include:– Implementation of thin wall boundary condition for finite
conductivity walls [Müller,2001]– Implementation of wall functions [Muck,2000][Pothérat,2002] for
Hartmann surface layers (work in cooperation with Alban Pótherat and Vincent Dousset of Coventry University)
![Page 15: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/15.jpg)
152008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
BB channels CFD modeling
• Tritium post-processing as a passive scalar has been implemented and is in a validation process. One difficulty is the low diffusion coefficient (DT~10-9 m2/s) which makes numerical diffusion to be dominant.
• Appearance of lateral surface layer MHD instabilities must be analyzed in detail.
• In general the results obtained with OpenFOAM as a MHD tool are satisfactory.
• Work performed to date is key to future development that should allow the full CFD simulation of liquid metal TBM.
![Page 16: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/16.jpg)
162008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
BB channels CFD modeling
![Page 17: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/17.jpg)
172008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
BB channels CFD modeling• 3D application (4 nodii in Hartmann surface layer, 10 in
lateral surface layer), total 777600 control volumes• Re=480 Ha=1740 Gr=2.3·107 and Sc=134• Purely hydrodinamic case
Some instabilities appear that are damped when a magnetic field is introduced
• Temperature-MHD case (not shown):Due to buoyancy, vortices appear, further analysisi needed
U (m
/s)
U (m
/s)
C (m
ol/m3)
C (m
ol/m3)
ST = 6.64·10-12 r -1.2473 mol/m3 s
![Page 18: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/18.jpg)
182008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
• Currently there do not exist experiments considering all the phenomena (MHD, heat transfer, tritium and helium)
• Experimental data for uncoupled phenomena (MEKKA, LIBRETTO irradiation tests)
• This fact makes code validation difficult .• An international effort exists (F4E) aiming to
the development of computational tools able to simulate the TBM channels.
BB channels CFD modeling
![Page 19: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/19.jpg)
192008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Auxiliary Systems for BB
Pb-Li Ancillary System for HCLL TBM
Main goals:• To develop PbLi Ancillary System for the HCLL TBM
• To develop PbLi Purification System to be incorporated in the PbLi ancillary system (e.g. cold trap, magnetic trap,…)
• Study of underlying processes (e.g. PbLi purification, corrosion products transport – dissolution & deposition, impurities behaviour, transmutation products formation and behaviour,…)
• Development and testing of suitable components (e.g. PbLi pump, connecting flanges, valves, diagnostics,…)
![Page 20: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/20.jpg)
202008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Specification for the PbLi ancillary system
• PbLi mass flow in the range: 0.1-1 kg/s (0.3 kg/s is approx. 10 recirculation per day)
• PbLi temperature range: 300-550°C• PbLi mass flow through the purification unit: TBD (estimated approx. 10% of
total flow)• Inert atmosphere: Argon• Maximum pressure in the system: 8 MPa (He leak from HCS)• System structure material: ferritic steel (Cr 10-12%) • PbLi composition:
– Pb-15.7at%Li eutectic alloy– Intermetallic compounds (e.g. PbLi)– Structure material corrosion products (e.g. Fe, Cr, Mn, Ni)– Impurities (e.g. Bi, Sn, Si, Al,…)– Impurities transmutation products (e.g. Po, Tl, Hg,…)
Auxiliary Systems for BB
![Page 21: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/21.jpg)
212008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Pb-Li ancillary system flow diagram
Tank
LDT
CT
TBM
TC
TC
TC
TC
TC
TC
TC
TC
TC
TC
TC
TC
TC
TC
TC
Q1
P
20 kW
20 kW
TC
max. 0,6 m3
Gas injection
Gas injection
Pb-17Li
Flow diagram of the Pb-17Li ancillary circuit
LEVEL
Q2
Q3
TC
TC
TC
TCHe purge TC
V1
V2
V3
V4
V5
V6
V11
V7
V8V10
V12
V9
V15
V13
V14
1 Ro1 Ro2
Ro3Ro4
Ro5
Ro6
Ro7
Ro8
To1
To1
Ch
MCP
Gas
Pb-Li system box
HCLL TBM
Pb-Li tank
Mechanical circulation pump
Heating
Cold trap
Detritiation unit
Sampling
Connection flanges
CT draining
Pb-Li draining
HCLL TBM Pb-Li auxiliary system (1)
PbLi filling
Flow diagram of Pb-17Li ancillary circuit
Conceived and designed NRI-IPP. Chek Rep.
The PbLi auxiliary system should ensure feeding and circulation of PbLi liquid metal in the breeding blanket and removal of tritium produced by a nuclear reaction in TBM.
![Page 22: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/22.jpg)
222008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
HCLL TBM Pb-Li auxiliary system (2)
Views of Pb-Li ancillary system box
The PbLi circuit is a closed loop with a slow forced circulation of PbLi. Main components are:• a PbLi feeding and storage tank, • a liquid metal pump (variable flow velocity 0.1 to 1 kg/s),• a detritiation unit to remove Tritium from PbLi (R&D still ongoing),• a cold trap to remove corrosion products and impurities (R&D still ongoing).
The container with the PbLi auxiliary system (dimensions H x L x W: 2.315 m x 2.19 m x 1.6 m) will be placed in the port cell
Conceived and designed NRI-IPP. Chek Rep.
![Page 23: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/23.jpg)
232008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
DCLL power extraction system (interest of Sp. Nat. Program)
• A system TH code, like RELAP5-3D, will allow the formulation of the main mass and energy balances.
• Interest on advanced HEX 2 (LM 2ry SC-CO2).
•Interest on compact permeators against vaccum
• Interest on two phase models (helium bred in LiPb)
![Page 24: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/24.jpg)
242008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Auxiliary systems modeling
• Challenges– Tritium and helium transport– Magnetic field– Complex geometries
• A RELAP5-3D model has been developed at UPC of a hypothetic two-fluid experimental facility (partially inspired in Mekka)
• Double loop: NaK/He
![Page 25: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/25.jpg)
252008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Auxiliary systems modeling
Heat up during initial transient
![Page 26: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/26.jpg)
262008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Auxiliary systems modeling
• Difficulties:– MHD head losses (it seems like RELAP5-3D should
compute them, but it does not) have been not considered at the moment. They could be introduced as Re dependent form losses.
– NaK used instead of PbLi, not only because it is the fluid in Mekka but because PbLi property tables are not available in our Athena version.
– No axial fluid conduction.
![Page 27: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/27.jpg)
272008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Compatibility of EUROFER with Pb-Li• Compatibility tests at different Pb-Li temperatures 480-550°C and
flow velocities 1-30 cm/s; HCLL TBM conditions• Various test facilities used (Picolo at FZK, LIFUS-2 at ENEA
Brasimone, Pb-Li facility at NRI Czech Rep.)• Effect of magnetic field (1.7 T) on EUROFER corrosion in flowing Pb-
Li (Latvia)
PICOLO loopEMP = Electromagnetic PumpFM = FlowmeterTS = Test SectionEH = Electrical Heater AC = Air coolerCFHE = Counter Flow Heat Exchanger
MT = Magnetic Trap
LIFUS-2 loop
ENEA-Brasimone
FZK
EU experimental facilities
![Page 28: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/28.jpg)
282008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
MHD experiments with a HCLL Mock-Up in the MEKKA
laboratory at FZK
Form-closed barriers
Design of the experiment4 breeder units, poloidal manifold, access tubes
MEKKA laboratory
EU experimental facilities
![Page 29: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/29.jpg)
292008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
The TRIEX Facility: test of Tritium extractor, ENEA Brasimone- Nominal mass flow
rate: 0.2 kg/s
- Maximum temperature: 500°C
- Minimum temperature: 350°C
- Stripping gas: Argon
- LM inventory in the loop: about 25 l + 80 l in the circulation tank
EU experimental facilities
![Page 30: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/30.jpg)
302008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Conclusions
• If nuclear fusion has to be a major source of energy in the future it is necessary to overcome some important challenges facing the international scientific community today.
• Several areas of technological knowledge are involved in the design of presently conceived fusion reactors, and brought to their limits.
• One of the most technology demanding components is the Breeding Blanket Module, together with the associated Tritium Extraction System.
![Page 31: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/31.jpg)
312008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Conclusions
• UPC and CIEMAT, together with other Spanish organizations, are trying to acquire de simulation capabilities needed to design and to analyze such complex systems.
• Simulation efforts focus in two lines:– MHD modeling of the BB channels (involving
tritium transport and heat transfer)– System code modeling of the whole BB
system (power extraction + ancillary systems)
![Page 32: Contents of the presentation](https://reader034.fdocuments.us/reader034/viewer/2022051821/5681592d550346895dc65a87/html5/thumbnails/32.jpg)
322008 RELAP5 Users Seminar, 18-20 Nov, Idaho Falls, USA
Conclusions
• CFD modeling is progressing at good pace, and results to date are encouraging. Though much effort still needs to be devoted to it.
• System code simulation is just starting. The success will depend on our ability to take advantage of the existing code capabilities, and the possibility of improving the existing codes.