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SEMINARIO ENEA - CASACCIA Venerdì 12 marzo 2010 ore 10 Carlo Artioli carlo.artioli@enea.it Multi-physics paramet

SEMINARIO ENEA - CASACCIA Venerdì 12 marzo 2010 ore 10 Carlo Artioli carlo.artioli@enea.it Multi-physics parameters optimization of ADS core for transmutation. IP-EUROTRANS International training course (ITC-9) on Accelerator–driven Transmutation System for

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SEMINARIO ENEA - CASACCIA Venerdì 12 marzo 2010 ore 10 Carlo Artioli carlo.artioli@enea.it Multi-physics paramet

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  1. SEMINARIO ENEA - CASACCIA Venerdì 12 marzo 2010 ore 10 Carlo Artioli carlo.artioli@enea.it Multi-physics parameters optimization of ADS core for transmutation

  2. IP-EUROTRANS International training course (ITC-9) on Accelerator–drivenTransmutation System for European and Asian Young Scientists and Engineers NuclearTechnology and Education Center JAEA, Tokai, Ibaraki, Japan Dec. 1-4, 2009 Multi-physics parameters optimization of ADS core for transmutation Carlo Artioli carlo.artioli@enea.it IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli Int’l Conference on Peaceful Uses of Atomic Energy New Delhi, Sept 29-Oct 1 / ENEA-BO 12 Nov 009 Carlo Artioli

  3. U-free Core design of the EFIT-Pb and of the Gas backup option SIXTH FRAMEWORK PROGRAMME EURATOM Management of Radioactive Waste IP EUROTRANS EUROpean Reserch Programme for the TRANSmutation of high Level Nuclear Waste in an Accelerator Driven System (ADS) DM0 DM1 … DM5 Management Design Nudatra WP1.1 WP1.2 ….. WP1.6 Reference Design Development and Assesment XT-ADS Remote Specifications of XT-ADS and EFIT Designs Handling Catalogue (ENEA, FZK, Ansaldo, CEA, Framatome ANP, NNC, CRS4) Task 1.2.1 ….. Task 1.2.4 …. Task 1.2.6 IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  4. EUROTRANS DM1 Task 1.2.4:EFIT Core Design (European Facility for Industrial Transmutation,) VI FP, IP EUROTRANS concept developed for the transmutation of MAs EFIT Pb Main features Goal: fissioning MA, while producing energy Fuel: MA & Pu Oxide in inert matrix (MgO) Coolant: Lead, Tin=400 °C, Tout=480°C Power: several hundreds MW IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  5. Kmax =0.97 High amount of MA allowed in the core IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  6. n IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  7. Main questions to be answered • Whatexactlymeans “burning MA at best” ? • 2) In which way the burningcapabilityhastobeoptimized? 3) What about the two goals: “burner” and “energy producer”? (should they be contradictory) IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  8. What exactly means “burning MA at best” ? (e.g.65) MA balance Kg (MA) /TWh Euro / Kg (MA transmuted) Coresize (MW) (e.g.400) IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  9. What exactly means “burning MA at best” ? MA balance Kg (MA) /TWh Core size (MW) Power density roughly invariant Power size become geometrical size Lattice ruled by linear power rating and TH constraint IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  10. What exactly means “burning MA at best” ? MA balance Kg (MA) /TWh Core size (MW) MA Pu fuel Pu Pu MA MA IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  11. IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  12. Small size, high enrichment Small size = low MA reaction rate Transmutation MA Pu Transmutation fission fission Large size = high MA reaction rate Large size, low enrichment Transmutation MA Pu Transmutation fission fission IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  13. Kg/TWh FUEL FUEL Ex. - 60, +18 MA mass balance e = Pu / (Pu+ MA) e = Pu / (Pu+ MA) Pu breeder - 42 0 Transmutations MA MA Pu Pu Pu burner Fission product Pu mass Balance Ex. - 30, -12 Total balance ≈ - 42 kg / Twhth (from theor. 210 MeV/fission) IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  14. What exactly means “burning MA at best” ? • A MA balance lower than -42 kg/TWh (e.g. -50) means that: • - 42 have been actually fissioned and • the difference (e.g. 8) have been transmuted in new Pu the system would act as Pu breeder • A MA balance higher than -42 kg/TWh, e.g. -35, means that: • - 35 have been actually fissioned and • the difference (e.g. 7) are fissions of Pu the system would act as Pu burner IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  15. What exactly means “burning MA at best” ? • In both the cases: • Producing new Pu and • Burning Pu • the system has not been optimized because there are “expensive” neutrons used not to fission MA. (Producing or fissioning Pu can be made in cheaper way in conventional reactor) • The best ADS, as MA burner, shows a: • MA balance of -42 kg/TWh and (of course) • Pu balance of 0 kg/TWh IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  16. 2) In which way the burning capability has to be optimized? 3) What about the to goals: “burner” and “energy producer”? (should they be contradictory) • The best ADS, as MA burner, shows a: • MA balance of -42 kg/TWh and (of course) • Pu balance of 0 kg/TWh Since looking for a MA performance “better” than -42 kg/TWh is meaningless, the optimization leads to the minimum cost of the TWh or considering the velocity of burning -42kg/h /TW the minimum cost of the power deployed which is the same optimization required for the energy production IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  17. How to get the : • MA balance of -42 kg/TWh and (of course) • Pu balance of 0 kg/TWh Kg/TWh Ex. - 60, +18 MA mass balance X kg/TWh of net Transmutations Pu breeder - 42 0 MA Pu X kg/TWh fissioned 42-X kg/TWh fissioned Pu burner FP, 42 kg/TWh Pu mass Balance Suitable e = Pu / (Pu+ MA) Ex. - 30, -12 The burning performance depends on the mutual ratio between Pu and MA i.e. on the enrichment IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  18. DESIGN OUTPUT INPUT to be supplied Main statement: kswing = 0 42 - 0 Pu and MA vectors Search of suited Pu/ (Pu+MA) Pu, MA dioxyde stechiometry and density; Matrix, density and fraction Definition of “enrich.” Pu/ (Pu+MA) Pellet composition Gas releases = f (T, BU) Verification and optimization Pin geometry definition (diameter and other by guess) Fuel density power Max linear power, TH (Tmax, conductivity law) Fuel element definition Core density power Keff required Core definition Core size and power IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  19. Which are the correlationships among the main core parameters (A-BAQUS graph) Matrix rate Enrichment Dk cycle Power/size Performances Current IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  20. e = Pu / (Pu+ MA) %MgO = Matrix / (Matrix + fuel) ( %fuel ) Which are the correlationships among the main core parameters e (%) PELLET MgO MA Pu 50 Inert matrix fuel %MgO 50 IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  21. ( %fuel ) Which are the correlationships among the main core parameters Kg/TWh e (%) e = Pu / (Pu+ MA) FUEL Ex. - 60, +18 MA mass balance Approximation: No effect on the spectrum of the variation of the matrix fraction (in the range) Pu breeder - 42 0 Transmutations 50 MA Pu Pu burner Fission product Total balance 42 kg / Twhth Pu mass Balance Ex. - 30, -12 %MgO 50 IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  22. e = Pu / (Pu+ MA) ( %fuel ) Which are the correlationships among the main core parameters Kg/TWh e (%) FUEL Dk (pcm/y) MA mass balance DK swing (pcm/y) Pu breeder Fission - 42 0 Fission 0 Transmutations Pu burner MA Pu Pu mass Balance %MgO 50 50 IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  23. Coolant volume fraction (depending on coolant velocity) Linear power rating (depending on the fuel) Homog. Power density rather constant ( %fuel ) Which are the correlationships among the main core parameters e (%) 50 %MgO IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  24. Homog. Power density rather constant IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  25. Coolant volume fraction (depending on coolant velocity) Linear power rating (depending on the fuel) Homog. Power density rather constant ( %fuel ) Which are the correlationships among the main core parameters e (%) 50 %MgO 200 enrichment constant decreasing %fuel (incr. %MgO) Increases the geometrical size (to adjust for criticallity) Core Radius (cm) 400 Increases the Core Power P (MW) IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  26. Subcriticality fixed! Which are the correlationships among the main core parameters I (mA) 50 25 Core Power Proton current 200 Dk swing Enrichment constant Proton current range Core Radius (cm) 400 P (MW) IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  27. Which are the correlationships among the main core parameters IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  28. EFIT-Pb Technology constraints Fuel CERCER (Pu,MA)O2-x-MgO inert matrix (or 92Mo , 93%enriched) % VF of MgO>50% (to assure thermal conductivity); Linear power <180-200 W/cm (depending on %VF MgO). - FA residence time = 3 years (Pb corrosion is the most restricting condition) T limit for the fuel:~1650 K (500 K below the inert matrix melting/disintegration) T limit for the cladding at nominal cond. (9Cr1MoVNb steel T91): 820 K Pb speed at 1 m/s (to limit corrosion effects) Active height = 90 cm (to limit the pressure drop) IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  29. , • FA dimensions are driven by the size of the spallation module, Rtarget = 43.7 cm (to replace 19 FAs) • Maintain a low keff swing during the cycle (no oversize of target and accelerator) • Maximize the power density • Decrease the form factors to flatten the coolant Tout (Pb at 750 K and <820 K for the cladding) and to maximize the avg power density by use of 3-zones with increasing active fuel volume fraction along the core radius (enr. Is fixed): • from inner to intermediate zone by increasing the fuel/matrix from 43% to 50% (but same pin diameter) • from intermediate to outer zone by increasing the pin diameter (and same fuel/matrix %) Design choices, rationales and solutions • Maximize MA fission. The enrichment is fixed to fulfil the “42-0” approach, i.e.: • 42 kg/TWhth is true for any nuclear system (it comes from 210 MeV/fission) • what is the policy about Pu? The choice here is neither Pu production (not consistent with U-free) nor Pu reduction (net fission expensive in ADS) • the choice is then to dedicate all the fissions (directly or indirectly) to MAs: net balance is -42 kg/TWhth for MA and 0 kg/TWhth for Pu (which sustains in any case the reactivity, acting as a catalizer) IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  30. Project parameters (as inputs) • Thermal power of some hundreds of MW (to be optimized) • Pb coolant for the proton target and the core (fast spectrum). Pb temp. for the core: Tin=673 K, Tout=753 K • External proton beam of 800 MeV up to 20 mA (windowless target) • Sub-critical level of keff = 0.97 (to be verified a posteriori) • The fuel is U-free and uses Pu and MA vectors. MA come from the spent UO2 (90%) and MOX fuel (10%) of a PWR (45 MWd/kgHM) with 30 cooling years. Pu from UO2 with 15 cooling years (data from CEA). IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  31. Radial flattening by increasing fuel volume fraction B: pellet with different fractions of matrix A: reduction of coolant volume fraction (larger pin) Tout , Tout Plin Outer zone Toutmax F, DP Coolant volume fraction Increasing fuel volume fraction IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  32. F u e l C o o l a n t Structural Pu+MA Matrix F u e l C o o l a n t Structural F u e l Pu+MA C o o l a n t Structural Matrix Pu+MA Matrix Inner zone by different matrix% and same pin PDfuel=max; Plin=max; Tout=max Reference Intermediate zone Flattening Techniques PDfuel=max; Plin=max; Tout=max Outer zone by different pin size and same matrix % PDfuel< max; Plin< max; Tout=max Pin “size” to obtain the same max PD but Tout should be unacceptable IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  33. Inner, Intermediate & Outer FA Design Inner and Intermediate: Outer: Same pin & pitch;  MgO VF (57%, 50%) > Pin  - Same MgO VF (50%) IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  34. Cylindrised vertical section&H3D model 384 MWth core 42 66 72 IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  35. Hom. Power density at midplane (calculations: M. Sarotto) Maximum allowed, corresponding to linear power rating 207 and 180 W/cm IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  36. BOC Monte Carlo Calculations (calculations Carlo Petrovich) To be considered in optimization step: reducing the core/spallation size the efficiency will be increased IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  37. BU = 78,28 MWd / kg (HM) BU-40,17 kg (MA) / TWh Total E = 10,0915 TWhth -1,74 kg (Pu) / TWh 3 years MA and Pu balances DMA / MA (BOC)  -13,9% DPu / Pu (BOC)  -0,7% IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  38. BU = 78,28 MWd / kg (HM) BU-40,17 kg (MA) / TWh Total E = 10,0915 TWhth -1,74 kg (Pu) / TWh 3 years Pu, MA vectors evolutions MA and Pu balances DMA / MA (BOC)  -13,9% • The Pu and MA vectors evolve in the time toward equilibrium configurations; this implies: • - Calculation of the enrichment with the equilibrium vectors • Enrichment resettings in the transitory phase DPu / Pu (BOC)  -0,7% IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  39. Power size optimization criterion: minimum cost / kg of fissioned Minor Actinides minimum cost per MW deployed. • cost / MWdeployed = f(core size, accelerator size) • - Core term: decreases increasing the power (if power density is const.); • Accelerator term: decreases increasing the power, • but the target loses efficiency. Present criterion: The largest size core acceptable within the current spallation module design (max power: 11.2 MW). IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  40. 3 approaches Starting M a i n p a r a m e t e r s Performancies point (kg/TWh) (- 42 TRU) e Dk cycle P(MW) i (800 MeV) (%) (pcm) (MW) (mA) DKzeroreactivity swing ≈ 0 400MWP = 400 MW 42-0D Pu ≈ 0 IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  41. 3 different approaches Graphical extimations IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  42. 3 approaches Starting M a i n p a r a m e t e r s Performancies point (kg/TWh) (- 42 TRU) e Dk cycle P(MW) i (800 MeV) (%) (pcm) (MW) (mA) DKzeroreactivity 50 ~0 275 ~ 7 ~ -36 MA swing ≈ 0~ -6 Pu 400MWP = 400 MW 27 ~ +2000 400 ~ 32-18 ~ - 65 MA ~ +23 Pu 42-0D Pu ≈ 0 45.7 ~ +500 395 ~ 16-14 ~ - 41 MA ~ -1 Pu IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  43. “42-0 Concept” Main conclusions • Conceptual “42-0” design leads to the best MA burner • in the sense that each fission is devoted to an “atom” • of MA, no matter the kind of ADS • The doubble goal, to be a burner and a producer of energy, • are not in conflict • Both can be reached minimizing the cost of the unit of energy • produced in the “42-0” concept IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  44. “EFIT-Pb” Conclusions The “42-0” strategy has been the fundamental approach for the neutronic design of the EFIT core. Simultaneously a low keff swing is obtained (small current excursion). MA fission (about 120 kg/year) via an U-free lead-cooled ADS as EFIT (384 MWth) is viable, as the core is concerned: acceptable max T for fuel and cladding in nominal conditions and transients. The safety analysis (including sub-criticality level choice) has anyway to be completed. Use of CERMET fuel (Mo matrix instead of MgO), qualification of fuel, steel in Pb environment, cost/benefits ratio are to be investigated. IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

  45. IP-EUROTRANS International training course (ITC-9) on Accelerator–drivenTransmutation System for European and Asian Young Scientists and Engineers NuclearTechnology and Education Center JAEA, Tokai, Ibaraki, Japan Dec. 1-4, 2009 Thank you Multi-physics parameters optimization of ADS core for transmutation Carlo Artioli carlo.artioli@enea.it IP-EUROTRANSInternational Training Course (ITC-9) Dec. 1-4, 2009 JAEA, Tokai, Ibaraki, JapanCarlo Artioli

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