J.M. Perlado, Integral study of IFE Power Plant based on Direct Drive and Non-Protected Chamber (HiPER) J. Manuel Perlado

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1 Integral Study of IFE Power Plant based on Direct Drive and Non-Protected Chamber (HiPER) J. Manuel Perlado Instituto de Fusión Nuclear (DENIM) ETSII/Universidad Politécnica Madrid Jose Gutierrez Abascal, 2, Madrid, Spain Seventh IAEA Technical Meeting (TM) on Physics and Technology of Inertial Fusion Energy Chambers and Target, Vienna, March 18-20, 2015

2 JMPM1 Team in this work J. M. Perlado 1, R. González-Arrabal 1, A. Rivera 1, E. del Rio 1, C. Guerrero 1, N. Gordillo 1, O. Peña 1, C. Gonzalez 1, D. Cereceda 1, R. Juarez 1, 2, M. Panizo 1, A. Prada 1, A. Rodríguez-Páramo 1, G. Valles 1, P. Diaz 1, F. Sordo 1, C. Sánchez 2, J. Sanz 1, 2, M. Velarde 1 1 Instituto de Fusión Nuclear (DENIM)/ETSII/Universidad Politécnica, Jose Gutierrez Abascal, 2, Madrid, Spain, josemanuel.perlado@upm.es Departamento Ingeniería Energética, ETSII, UNED, Madrid, Spain

3 Slide 2 JMPM1 Jose Manuel Perlado Martin,

4 Contents EOS of Hydrogen at cryogenic and high pressure conditions Study of Blanket and Reactor (HiPER) Types of design Proposals of Chamber depending on Cooling Options Tritium and Neutronics Activation of Coolant Fluid-Dynamics Corrosion Power Plant

5 Laser compresiondt 1x10 6 K K To3000 K 300 GPa 1000 GPa 100 GPa 10 ps-1000 ps

6 Potential change of mechanical properties because of Segregation of Ablator (Be) in Fuel Elastic Constant H vs H_Be (different behaviour of ortoghonal and shear axis) ++ Ab Initio Simulation Beryllium in Solid Molecular Hydrogen: Elastic Constant. C. L. Guerrero and J. M. Perlado 2015, Journal of Physics

7 Crystal Structure: H vs H_Be The additional Be produces a different (larger) ordering in the molecular solid H structure which is observed in H at higher pressures. Higher ordering coming from additional Be.

8 Bulk Modulus for Solid Molecular Tritium: ab initio approximation. C. Guerrero and J.M Perlado SOFE 2014 Key magnitudes in manufacturing: 1) rugosity of DT sphere surface; 2) thickness of DT shell, quality control and spherical shape; 3) co-existance of solid and liquid phases (in storage); 4) changes between HCO and FCC phases giving discontinuities in the solid; 5) appearance of unstable phases HCP_FCC, observed in target manufacturing and reconginezed as semi-stable (A. HAMZA group PRL 2011) Scheme of the causes related with the fabrication and handling of DT ice target and growth of hydrodynamic instabilities during the ignition process. The process has 3 parts: A) defines a mixing H2, D2, T2, HD, HT, DT, HDT you want to model. B) apply the energy minimization by two methods: the conjugate gradient (for 0 K) and QMD temperature, with Nose-Hoover thermostat only, C) finally with QMD Parrinello-Rahman barostat and N-H thermostat is set the temperature and pressure, increase or decrease in pressure is achieved by applying different ramps up or down. Our initial structurearoundtheallstudy ishcpasshowninparta.thesimulationismade with 576 atoms in PBC conditions. With this first process we obtain the atomic structure for temperature and pressure determinate. Additional results also get energy from the configuration, the forces and the stress tensor of the simulation box, through which we calculate the mechanical parameters such as the elastic constants and bulk modulus.

9 Bulk Modulus for Solid Molecular Tritium: ab initio approximation. Carlo Guerrero and J.M Perlado SOFE 2014 Validation of Model with H TRITIUM BULK MODULUS CALCULATION (few determinations in literature) HYDROGEN 3OO K TRITIUM 300 K

10 Ab Initio Calculation of the Speed of Sound for Mixtures of Solid Molecular Hydrogen-Deuterium (HD) In the solid molecular state these changes in sound speed and bulk modules are related to configuration changes orientational HD molecules, we've already seen in the H. We focused our study at 15 K to be close to the triple point of hydrogen, condition in which target are held ICF prior to ignition and at this temperature and in the range of 10 GPa to 180 GPa be presented Phase transitions I-II-III. Obtaining bulk modulus and sound velocity helps us to build more accurate state equation, which represent the changes in the molecular orientational H, HD and DT.

11 Relation between structural phases and the speed of sound in dense hydrogen

12 PHASE 0: Allow more free movement of MOLECULAR ROTOR out of its crystal position which can explain the mixing of two phases HCP and FCC (observed but need more experimental demonstration) This phase is not analyzed but reported previously explained in a simple way the system can be converted HCP in FCC, and further explained some inhomogeneities obtained in manufacturing targets for ICF. This analysis result is still in yet fits some of the discontinuities and fluid released for solid phase transitions.

13 Proposals Studied Garozet al, Nucl. Fus. (2013)

14 Scheme for HiPEREngineering Colaboration with Stephen Sanders / Oxford Technologies, UK

15 Reactor Layout

16 Computational Methodology 1 CATIA 2 3 MCAM MCNP FLUENT 4 5 ACAB 1. 3D Geometries generation 2. Conversion to MCNP input format 3. Neutronic Fluxes and Nuclear Heating 4. Temperatures calculation and Corrosion rates 5. Calculation of Isotopic Inventory Key Magnitudes

17 Objetives With technologies developed in HiPER Engineering: 1. Reactor of 1500 MWth 2. Uniform Direct Drive Ilumination 3. Dry Wall First Wall (R=6.5m, 1 mm W) Our Work: Select Technological Scheme Adapting previous knowledge to HiPER REACTOR conditions Combined study of neutronics, fluid-dynamics, power cycles

18 SCLL Blanket for HiPER Reactor SCLL based on EUROFER 97 and LiPb Preliminary decission: all structural components of the ducts of 2 cm thickness

19 Two options of Chamber cooling Proposal for HiPER: Cooling of First Wall IFWB: LiPb extract 100% of heat in chamber SFWB: FW has an independent He circuit and it is separated from blanket. LiPb in Blanket.

20 Chamber Cooling FW cooling IFWB: W armour is build over the internal face of blanket. SFWB: W armour is build over a blanket independent substrate of EUROFER97-ODS

21 Tritium Breeding Ratio Criteria Criteria TBR=1.1 Tritium Breeding Ratio TBR vs. Breeder thickness Breeder Thickness (cm) 30% 50% 70% 90% Two options considered: 1. Thick blanket: 75 cm breeder thickness 25% Li enrichement 2. Thin blanket: 50 cm breeder thickness 70% Li enrichement

22 TBR=1.1 IFWB calculations for options of blanket: tritium inventory Thin blanket TBR Inner duct thickness 8 cm 8 cm Outer duct thickness 42 cm 67 cm Thick blanket LiPbvolume 310m 3 475m 3 (70% 6 Li) (25% 6 Li) h blanket TBRrange[10%-90%] Peso del LiPb 3100 Tm 4750 Tm Thin Blanket better from the weight criteria but more costly because of enrichement.

23 ModellingNeutronicsof Blanket Irradiation Thin blanket Thick blanket φ 1 (n/cm 2 s) φ 2 (n/cm 2 s) t 1 (s) 7 7 t 2 (s) n.cycles/yr

24 Generation of tritium in the LiPb Tritium inventory in the loop (g) Tritium inventory in LiPb loop Thick Thin partial pressure Permeator efficiency (%) Certainly, STRONG DEPENDENCE ON PERMEATOR EFFICIENCY. FIRST POTENTIAL OPTION 90% T partial pressure in the LiPb (mpa) 1. Tritium partial pressure in the loop is in both cases very low (3 mpa) for high permeator efficiencies. No spreading. 2. Total Inventory in the loop is very low in both cases (even more in thin blanket) (<0.1 g)

25 LiPbActivation 203 Hg activity (TBq) 210 Po activity (TBq) Total 203 Hg activity for both blanket options Thick blanket Thin blanket Irradiation Time (FPY) Total 210 Po activity for both blanket options Thick blanket Thin blanket Irradiation Time (FPY) During an accidental situation a certain fraction of those isotopes inventories can be mobilized and released. The relation between the inventory present and the maximum which could be released is the degree of radiological confinement (DRC), which will be demanded to the facility design. If this DRC is not viable with the implementation of safety systems, a purification system will be introduced to limit the content of Po, Bi and/or Hg in the LiPb. In this way it is guaranteed the no emission of isotopes above the limit. To avoid Evacuation plan, the limits are: 203 Hg 925 TBq 210 Po TBq Degreeof rad. confinement Thin blanket Thick blanket años años Thin blanket requires less radiological confinement

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27 He generation in the Vacuum Vessel Vacuum Vessel (VV) needs to be a Plant lifetime component. Reweldability guaratee for 40 years. Limit considered from Engineering consideration is < 1 appm of He in the external face of VV. He fpy option1 Thickblanket option2 Thinblanket VV thickness (cm) Thick blanket allow VV of thickness 39 cm, and Thin Blanket 52 cm. Too large thickness in both (thin and thick cases) It would be desirable < 20 cm thickness

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30 The design objective is that the LiPbwill enter the blanket at 350ºCthrough the thin duct, and will exit at 450ºCthrough the thick duct, keeping the corrosion rate as low as possible. The LiPbflow rate corresponding to that temperature rise is: 6.3 m 3 /s for the SFWB 8.5 m 3 /s for the IFWB,

31 The power coming out from our assumed burnupis 1500 MW (The (ions and the X-rays; 375 MW, neutrons 1125 MW). The power carried by the ions and X-rays is fully deposited in the first microns of the First Wall. Energy deposited by neutrons in Blanket is MW This withstands a blanket gain of =1.18.

32 Fluid-dynamics 39,84% 8,4 % ENERGY DEPOSITION BY NEUTRONS Stretch SFWB In LiPb deposition Neutron power deposition (MW) LiPb volume (m 3 ) Inlet pipe Thin duct Transition channel Thick duct Outlet pipe Total Arrangement Here the X-Rays-Cparticlesare INCLUDED Thin duct (MW) Thick duct (MW) Total (MW) IFWB SFWB

33 To overcome limitation of 550ºC because of EUROFER Mass of SFWB = 9685 Kg/s, with T = 514ºC (margin to 550ºC) In the case of IFWB, considering the ratio of Power to be evacuated in this case, which is a factor of 1,25 Mass of IFWB = Kg/s

34 Maximum Local Temperature SFWB o IFWB? Representation of Distribution in the Internal Sheet of the Thin Duct In case of SFWB T is less than 550ºC. With that flow the outer Temperature of LiPb is only of 395ºC In the case of IFWB, the critical point in the EUROFER can reach Temp(ºC) SFWB: 9658 kg/s IFWB: kg/s 670ºC (!!!!!)

35 Maximum Local Temperature SFWB o IFWB? Bad cooling because of Recirculation: 1. Obstacle (Laser Penetration) 2. 2D Flow (Thin duct) Section of high velocity (small area) 3. Deceleration Area Colaboration with J. Hernández y C. Zanzi

36 Turbulence Model: Large potential influence in Results Results for internal sheet of Thin Duct The turbulence model could overestimate the maximum temperature results

37 Criteria for Structural Integrity of Blanket components: No more than 10 % of SS thickness can be removed from blanket along lifetime Thickness of Sheet of Steel component of Flow Coolant container = 2 cm Assuming 5 years of lifetime = Maximum allowed is 200 µm/yr

38 Local Corrosion Rate SFWB o IFWB? Corrosion Limit = 200 µm/yr Maximum Corrosion rate in the SFWB is 650µm/yr Maximum Corrosion rate in the IFWB is 6500µm/yr Corrosion (µm/yr) SFWB: 9658 kg/s IFWB: kg/s While using the RANS model maximum local corrosion rates of 650 µm/yr were found, the same input changing to LES model gives 130 µm/yr!!!!!!!! Colaboración con J. Hernández y C. Zanzi

39 Corrosion rate Corrosion Rate normalized to that at 550ºC Corrosion Rate vs. Temperature 1.0E E E E E Temperature (ºC) Question and review: The Turbulence model used overestimate the corrosion 50ºC of difference corresponds to one order of magnitude in corrosion.

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41 Summary of Fluid-dynamics SFWB design is having a better performance than IFWBin: o o o Maximum Local Temperature máxima local Outlet average Temperature of LiPb Maximum Corrosion Rate Using the RANS turbulence model, SFWB presents a recirculation that gives a bad cooling. Inconsequence, a low outlet temperature and a corrosion rate 3 times higher than desired. After calculations with LES turbulence model, it appears a better behaviour (to be finally defined) reducing the bad previous results.

42 HiPER Reactor proposal SCLL based on EUROFER 97

43 He Brayton cycle for IFWB SFWB o IFWB? Intercooler Q LiPb Reactor HEx LiPb Helium Compressors He Turbine HX Regenerator Q Cooler η IFWB =37.5% Red

44 Brayton He Cycle for SFWB SFWB o IFWB? Intercooler Q He HX1 Reactor LiPb HX2 LiPb Helium He HX Compressors Turbine Red Regenerator Q Cooler η SFWB =38.5% +also better safety conditions

45 Conclusions EOS for H, D, T for manufacturing and handling processes have been studied using modelling and comparing with experiments Two Phases of HiPER studied: engineering/burst and Power Plant Self-Cooled Lithium Lead (SCLL) proposal for Blanket Two Options of SCLL: Integral First Wall Blanket (IFWB) and Separated First Wall Blanket (SFWB) Tritium Breeding Criteria: Thin and Thick Blanket Tritium Inventory: low in both concepts Activation of Hg and Po: a concern Study of Damage in Vacuum Vessel Determination of Maximum Temperature and Corrosion in EUROFER Influence of typical Turbulence Model in CFD larger than expected.