A high power ADS theoretical concept

Transcription

1 Technology and Components of Accelerator-Driven Systems A high power ADS theoretical concept 22/05/2013 Nicolas Thiolliere a Baptiste Mouginot a Jean-Baptiste Clavel b Arnaud Cadiou a Fanny Courtin a Amélie Pector a a - Subatech Laboratory, CNRS/in2p3, EMN, Univ. Nantes, France. b - IRSN, PSN-EXP, SNC, LNC, Fontenay-aux-Roses, 92262, France

2 OUTLINE Nuclear waste management in France The french law and the scenarios The «report 2012» The LAST-ADS concept Concept presentation Composition at Beginning of Cycle (BOC) Inner core size determination Thermal power calculation The fuel evolution The reactivity control Mass evolution and balance Conclusion and perspectives

3 OUTLINE Nuclear waste management in France The french law and the scenarios The «report 2012» The LAST-ADS concept Concept presentation Composition at Beginning of Cycle (BOC) Inner core size determination Thermal power calculation The fuel evolution The reactivity control Mass evolution and balance Conclusion and perspectives

4 Nuclear waste management in France The french law and the scenarios The nuclear high-level waste management research priorities are defined in the 2006 law. Three complementary areas have been defined : Partitioning and transmutation. Reversible waste disposal in a deep geological formation. Storage. First scenario family - transmutation in Sodium Fast Reactor: Homogeneous mode Heterogeneous mode

5 Nuclear waste management in France The french law and the scenarios The nuclear high-level waste management research priorities are defined in the 2006 law. Three complementary areas have been defined : Partitioning and transmutation. Reversible waste disposal in a deep geological formation. Storage. Second scenario family - transmutation in ADS: Double-strata approach

6 Nuclear waste management in France The «report 2012» Double stata scenarios have been performed with the 400 MW EFIT. Conclusions on transmutation in ADS High inventory in the cycle (reactors, treatment and fabrication plants) Transmutation capacity is too low : 18 ADS for a 60 GW SFR nuclear fleet. Technologically complex option. Involves an extra cost of 30%. Should we continue to study double-strata scenario involving ADS in France? ADS can play a role in long-term scenarios, such as nuclear phase-out Focusing on three key factors to improve ADS transmutation capacity: Increase the thermal power Increase the specific power Increase the irradiation cycle time { Decrease the ADS number Decrease the reactor inventory Decrease the cycle inventory

7 OUTLINE Nuclear waste management in France The french law and the scenarios The «report 2012» The LAST-ADS concept Concept presentation Composition at Beginning of Cycle (BOC) Inner core size determination Thermal power calculation The fuel evolution The reactivity control Mass evolution and balance Conclusion and perspectives

8 The LAST-ADS concept Concept presentation Liquid Annular Spallation Target ADS concept High frequency rotating magnetic field. 1 GeV cylindrical proton beam liquid lead spallation target. Inner/Beam/Outer core radius ~ 180/191/260 cm. Core height = 110 cm. k BOC = Assembly and pin geometry from BREST-300.

9 The LAST-ADS concept Composition at Beginning of Cycle (BOC) Fuel type : (Pu-MA)O 2. Inert Matrix : MgO. Improve thermal conductivity. Fuel dilution for reactivity control. Inert matrix fraction (Vol) : ~50%. Fuel density = 0.90 theoretical density. Density ~ 6.4 g/cm 3.

10 The LAST-ADS concept Inner core size determination Energy loss (a.u.) Homogeneous geometry simulation 3D MESH tally with MCNPX Spatial neutron flux Spatial deposited energy A regular deposited power in the sub-critical inner core can be achieved.

11 The LAST-ADS concept Thermal power calculation Thermal hydraulics hypothesis: Basic thermal hydraulic 2D-RZ model Heat and mass transfer equation Notter & Sleicher formula for lead Nusselt number Compound (HNO 2 ) X -(MgO) Y conductivity (λc) Bruggeman equation Heavy Nuclides conductivity neglected c =(1 F HNO2 ) 3/2 F HNO2 = HNO2 volume fraction. Maximum fuel pin temperature : 1800 K Liquid lead velocity : 2 m/s Inlet lead temperature : 700 K Maximum pin power : Maximum beam intensity : Maximum thermal power : P pin ~ 38 kw I max ~ 130 ma P max ~ 2.1 GW th Provided values are order of magnitude. Necessity of a complete uncertainty study.

12 OUTLINE Nuclear waste management in France The french law and the scenarios The «report 2012» The LAST-ADS concept Concept presentation Composition at Beginning of Cycle (BOC) Inner core size determination Thermal power calculation The fuel evolution The reactivity control Mass evolution and balance Conclusion and perspectives

13 The fuel evolution The reactivity control A fuel at equilibrium with multi-reprocessing of Pu and MA: k eff increases by ~4% during ~3 years. A fuel not at equilibrium with ~50% Pu and ~50% MA k eff decreases Adjust the ratio between Pu and MA to maintain the k eff

14 The fuel evolution The reactivity control A fuel at equilibrium with multi-reprocessing of Pu and MA: k eff increases by ~4% during ~3 years. A fuel not at equilibrium with ~50% Pu and ~50% MA k eff decreases Adjust the ratio between Pu and MA to maintain the k eff

15 The fuel evolution Mass evolution and balance Mass balance = (Final mass - Initial mass)/initial mass ΔM/Dt (kg/y) ΔM/M (/cycle) Am Cm Np Pu TOT MA TOT HN Americium and Neptunium are highly transmuted. Curium is created : The main contributor masses, 244 Cm and 245 Cm, are constant. 242 Cm (T 1/2 = 163 days) and 246 Cm (T 1/2 = 4760 years) are created. Plutonium mass evolution is constant : Odd isotopes, 239 Pu and 241 Pu decrease. Even isotopes, 238 Pu, 240 Pu and 242 Pu are generated. 238 Pu is by far the main contributor to the increase.

16 OUTLINE Nuclear waste management in France The french law and the scenarios The «report 2012» The LAST-ADS concept Concept presentation Composition at Beginning of Cycle (BOC) Inner core size determination Thermal power calculation The fuel evolution The reactivity control Mass evolution and balance Conclusion and perspectives

17 Conclusion and perspectives Conclusion French scenarios summarized in the «report 2012» are rather unfavorable to ADS: High ADS number High MA inventory in the nuclear cycle Increase the (specific)thermal power. Since 2009, a part of the ERDRE group at Subatech work on theoretical high thermal power ADS designs: Three targets concept Annular spallation target concept Liquid Annular Spallation Target ADS concept has an attractive neutronic behavior. Maximum intensity is around 130 ma and maximum thermal power reaches 2.1 GW th. Transmuted mass by ADS is close to 750 kg/year. Calculated parameters are order of magnitude and a complete uncertainty propagation must be carried out to confirm/infirm trends.

18 Conclusion and perspectives Perspectives System study on high thermal power ADS : Neutronic simulations : matrix : CERCER, CERMET. Fuel : Oxide, Nitride. Uncertainty propagation Preliminary Safety studies Safety coefficients Improve thermal-hydraulic study Mechanical feasibility LAST-ADS transmutation performance is dedicated to be tested in specific scenarios that will be performed with the code CLASS (Core Library for Advanced Scenarios Simulation). Scenarios with CLASS: Advanced MA Transmutation scenarios. Pu and MA management for Phase-out scenarios 2080? 2150?

19 The end Thank you

20 The end BACK-UP

21 Nuclear waste management in France Improving transmutation capacities Focusing on three key factors to improve ADS transmutation capacity: Increase the thermal power Increase the specific power Increase the irradiation cycle time Cooling and Fuel fabrication Mass ADS Number 10 ADS power (MW) 400 Reactors Fuel specific power (W/cm 3 ) 200 Cycle time (y) 3 Cooling time (y) 7 Time

22 Nuclear waste management in France Improving transmutation capacities Focusing on three key factors to improve ADS transmutation capacity: Increase the thermal power Increase the specific power Increase the irradiation cycle time Cooling and Fuel fabrication Mass ADS Number 10 ADS power (MW) 2000 Reactors Fuel specific power (W/cm 3 ) 200 Cycle time (y) 3 Cooling time (y) 7 Time

23 Nuclear waste management in France Improving transmutation capacities Focusing on three key factors to improve ADS transmutation capacity: Increase the thermal power Increase the specific power Increase the irradiation cycle time Cooling and Fuel fabrication Mass ADS Number 2 ADS power (MW) 2000 Reactors Fuel specific power (W/cm 3 ) 200 Cycle time (y) 3 Cooling time (y) 7 Time

24 Nuclear waste management in France Improving transmutation capacities Focusing on three key factors to improve ADS transmutation capacity: Increase the thermal power Increase the specific power Increase the irradiation cycle time Cooling and Fuel fabrication Mass ADS Number 2 ADS power (MW) 2000 Reactors Fuel specific power (W/cm 3 ) 400 Cycle time (y) 3 Cooling time (y) 7 Time

25 Nuclear waste management in France Improving transmutation capacities Focusing on three key factors to improve ADS transmutation capacity: Increase the thermal power Increase the specific power Increase the irradiation cycle time Mass Cooling and Fuel fabrication Reactors ADS Number 2 ADS power (MW) 2000 Fuel specific power (W/cm 3 ) 400 Cycle time (y) 3 Cooling time (y) 7 Time

26 Nuclear waste management in France Improving transmutation capacities Focusing on three key factors to improve ADS transmutation capacity: Increase the thermal power Increase the specific power Increase the irradiation cycle time Mass Cooling and Fuel fabrication Reactors ADS Number 2 ADS power (MW) 2000 Fuel specific power (W/cm 3 ) 400 Cycle time (y) 4 Cooling time (y) 7 Time

27 Nuclear waste management in France Improving transmutation capacities Focusing on three key factors to improve ADS transmutation capacity: Increase the thermal power Increase the specific power Increase the irradiation cycle time Mass Cooling and Fuel fabrication Reactors ADS Number 2 ADS power (MW) 2000 Fuel specific power (W/cm 3 ) 400 Cycle time (y) 4 Cooling time (y) 7 Time

28 BACK-UP Energy loss with different MgO Fraction

29 The fuel evolution The reactivity control Neutron gain = Neutron creation (n,f and n,2n) - neutron absorption (n,f; n,c and n,2n) G i = N i Z ( fi (E) i (E)+2 ni (E)) (E)dE N i Z ai(e) (E)dE Increase reactivity : 238 Pu 245 Cm 241 Am 242m Am 243 Am Decrease reactivity : 239 Pu 241 Pu

30 BACK-UP Notter & Sleicher formula for lead Nusselt number NS est valable pour des Pr compris entre 4.10^-3 et 0.1 et pour des Re entre 10^4 et 10^6. Pour du plomb à 350 C Pr=0.02 donc cote Pr ca doit etre bon. A verifier compte tenu de ta géométrie et de la vitesse d'écoulement si ton Re est bon... Tu trouveras des données plomb dans la these de Pilarski en ligne p132 :

31 BACK-UP BREST-300 to 1200 MW e lead-cooled pool-type reactor

32 BACK-UP CERCER Fuel

33 BACK-UP CERCER Fuel

34 BACK-UP CERCER Fuel