Status of HPLWR Development

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1 Status of HPLWR Development Thomas Schulenberg SCWR System Steering Committee Karlsruhe Institute of Technology Germany

2 What is a Supercritical Water Cooled Reactor? PH HP IP LP PH Produces superheated steam at supercritical pressure Once through steam cycle No steam generators No recirculation pumps No steam separators or dryers Follows the technology trend of fossil fired power plants Slide 2

3 Advantage: Higher Efficiency? 2015 HPLWR Slide 3

4 Advantage: Lower Costs Comparison of Containment Size - same scale - AP MW e BWR 1284 MW e HPLWR 1000 MW e 25 m 49 m 83 m Slide 4

5 280 C, 25 MPa 500 C Core Design Target Thermal power: 2300 MW th Coolant mass flow: 1179 kg/s Active core height: 4.20 m Thermal neutron spectrum Feedwater temp. 280 C Core outlet temp. 500 C Core inlet pressure 25 MPa Max. linear heat rate 39 kw/m Peak cladding temp. 630 C Target burn up 60 MWd/kg HM Evaporator Superheater 1 Superheater 2 Köhly et al., KIT (2009) Slide 5

6 Core Design Strategy A target hot channel factor of 2 would exceed the max. cladding temperature by far. Temperature [ C] liquid like inlet steam like Nominal enthalpy rise outlet Enthalpy [kj/kg] Hot channel Slide 6

7 Core Design Strategy Multiple heat up steps with intermediate coolant mixing eliminates hot streaks. Temperature [ C] liquid like inlet Evaporator SH1 steam like Hot Channel outlet Enthalpy [kj/kg] Slide 7

8 Fuel Assembly Design Concept Water box 40 wire wrapped fuel rods Spring Control rod spider Orifice at moderator water inlet Sealing ring 40 fuel rods d = 8 mm p = 9.44 mm Wire pitch 20 cm Assembly box 73.5 mm Head Piece of Assembly Cluster Slide 8

9 Foot Piece Design Control rod Fuel assembly Piston rings for sealing Coolant Outlets for moderator water Slide 9

10 Head Piece with Upper Mixing Chamber Upper mixing chamber RPV Reflector Slide 10

11 Core Arrangement Evaporator: 52 fuel assembly clusters, upward flow Superheater 1: 52 fuel assembly clusters, upward flow Superheater 2: 52 fuel assembly clusters, upward flow Slide 11

12 Equilibrium Cycle Analysis Year 1 Year 2 Year 3 Year 4 Shuffling Scheme Fresh fuel used primarily in the evaporator Cluster type Axial segment 235 U Enrichment [w/o] Gd 2 O 3 Basic Corne With Gd content r 4 Bottom Top Bottom Top Fresh fuel enrichment C. Maraczy et al., KFKI 2010 Slide 12

13 Power Distribution and Radial Form Factors at End of Equilibrium Cycle C. Maraczy et al., KFKI 2010 Radial Power Distribution Radial Form Factor Slide 13

14 Compensation of Power Peaks by Coolant Mass Flow Rate by Control Rods at BOC kg/s C. Maraczy et al., KFKI 2010 Only one orifice per cluster! Control rods only in 5 of 9 assemblies! Slide 14

15 due to power gradients Local Peaking Factors L. Monti, KIT 2009 E.g. Superheater 2 Assembly Peaking factors of fuel rod power Coolant peaking factors Slide 15

16 Local Peaking Factors due to control rods Gd-poison due to Gd Burn-out Begin of Cycle End of Cycle W.Bernnat, IKE 2010 Slide 16

17 Quality of Coolant Mixing in the Upper Mixing Chamber A. Wank, KIT 2009 Coolant Temperature Distribution Superheater 2 Outlets Evaporator Outlets Inlets Superheater C Superheater Inlet Mixing optimized by additional walls Evaporator Outlet Slide 17

18 Quality of Coolant Mixing in the Lower Mixing Chamber Coolant Temperature Distribution SH2 inlets C 450 Jets mixing feed water Swirl nozzles causing a ring vortex SH1 outlets A. Wank, KIT Slide 18

19 Operational Uncertainties E.g. by bending of an assembly box Peaking factors at 4.5 mm max. deflection T. Reiss, 2008 Limited with spacers to 0.5 mm max. W.Bernnat, IKE 2010 Slide 19

20 Design Concept of the HPLWR Safety System Passive containment condensers Containment isolation valves Automatic depressurization system Steam line Feedwater line 4 Upper pools Active low pressure coolant injection system Pressure suppression pool Residual heat removal Slide 20

21 Analyses of Safety System Performance Mass Flow Pressure Cladding Temperature Example: Automatic depressurization transient APROS Analysis M. Schlagenhaufer, 2010 Slide 21

22 Turbine building 2 Reheaters Design Concept of the HPLWR Conventional Island IP Turbine HP Turbine LP Turbine Generator Köhly et al Preheater Start-up system Drain tank and pump 4 Feedwater pumps Feedwater tank Slide 22

23 HPLWR Power Plant Concept (2010) Net Power 1000 MW, Net Efficiency 43.5% Designed and analyzed by AREVA NP, CEA, IKE, KFKI, KIT, NRG, PSI, VTT Slide 23

24 Key Technologies: Heat Transfer of Supercritical Water Numerical simulation of heat transfer phenomena in tubes and annuli Application of method to rod bundle geometries Wall temperature [ C] CFD analyses Palko 2008 Tube data Shitsman 1963 Chandra et al., NRG 2009 Bulk enthalpy [kj/kg] Predictions by correlations Wall temperatures in K Slide 24

25 Key Technologies: Materials for Fuel Claddings Test of available cladding alloys in Europe Oxide Thickness (µm) ,1 after 600h at 650 C P91 P92 ODS (FZK) ODS (EU) PM NG BGA4 800H IN 625 Not applicable because of low strength or high Ni content Very promising: Modified stainless steel 310 developed and tested in Japan Cr(%) VTT and JRC Slide 25

26 In-Pile Test of Cladding Materials up to MPa Effect of radiolysis and water chemistry on corrosion Measurement and Auxiliary Systems of the In-Pile Supercritical Water Loop at CVR, Řež M. Ruzickova et al. CVR Slide 26

27 Next: Test of a Small Scale Fuel Assembly under Supercritical Water Conditions In-Pile Test in the LVR-15 Research Reactor in the Czech Republic Out-of-Pile Test in the SWAMUP Test Facility at SJTU Shanghai Supported by a European- Chinese Collaborative Project Slide 27

28 Status of R&D for the High Performance Light Water Reactor Conceptual design of the HPLWR reactor including safety systems, containment and steam cycle component completed. A large number of steady state and transient analyses of the core, the reactor, the safety systems, and plant control confirm the viability of the concept. Codes and methods for prediction of global and local phenomena are ready. Available cladding materials are applicable up to 550 C. Better materials will require more R&D IAEA Advanced Reactors Information System (ARIS) Final Report: Slide 28