Derde Generatie Kerncentrale voor Nederland

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Tobias Hermans
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1 Derde Generatie Kerncentrale voor Nederland Physics of Nuclear Energy Jan Leen Kloosterman Delft University of Technology vision from Nuclear fission Distribution of energy radioactive Fissioning of 1 gram uranium yields as much energy as burning 2500 liters petrol or 3000 kilograms coal 3 4 Fission product distribution Fission probability of Uranium 10 2 LW R U-235 Pu-239 Sr-90 Yield (%) Pu-241 I-131 Cs-137 Fission probability Mass number A Neutron energy (MeV) 2200 m/s km/s 5 6

2 Enriched fuel U-238 U-235 Uranium enrichment 99,3% 0,7% Natural uranium 96% 4% 4% enriched uranium in nuclear fuel 7 8 Nuclear fuel U-235 neutron Moderator U-238 U-235 Pu-239 Moderator Pu Pressurized Water Reactor Boiling Water Reactor Borssele Dodewaard 11 12

3 Important components in a PWR Pressure vessel of a PWR 12 m 4 m Pressurizer of a PWR Steamgenerator of a PWR 20 m Replacement steamgenerator Boiling Water Reactor (BWR) 17 18

4 Safety of Nuclear Energy Reactor safety Feedback coefficients Control of fission chain reaction Fuel cooling (in and outside reactor pressure vessel) Confinement of radioactivity U-235 Moderator Moderator feedback Doppler feedback U-238 U-235 1) Stable system Pu ) Loss of coolant stops fission chain reaction 3) Loss of moderation stops fission chain reaction 22 Control rods Decay heat production Decay power / MWth Decay energy / MWd 23 Time / day Also after shut down of the reactor, the fuel needs to be cooled for a long time! 24

5 Decay heat production Reactor building Decay power / MWth Vervalenergie / MWd 300 kg/mwth water@sbp waterbassins Time / day 25 June 22, Containments nuclear power plant Fukushima 2011 Fuel rod Primary system (steel) Containments (2x concrete+steel) Source: Matthias Braun, Areva 29 Source: Matthias Braun, Areva 30

6 15:41 14 m Source: Matthias Braun, Areva 31 Source: Matthias Braun, Areva 32 Source: Matthias Braun, Areva 33 Source: Matthias Braun, Areva 34 Source: Matthias Braun, Areva 35 Source: Matthias Braun, Areva 36

7 Source: Matthias Braun, Areva 37 Source: Matthias Braun, Areva 38 Source: Matthias Braun, Areva 39 Source: Matthias Braun, Areva 40 Source: Matthias Braun, Areva 41 Source: Matthias Braun, Areva 42

8 Source: Matthias Braun, Areva 43 Source: Matthias Braun, Areva 44 Source: Matthias Braun, Areva 45 Source: Matthias Braun, Areva 46 Fukushima Daiichi Spent fuel pools Source: Matthias Braun, Areva 47 Source: VGB Powertech 48

9 Spent fuel pools Spent fuel pools Source: Matthias Braun, Areva 49 Source: Matthias Braun, Areva 50 Generations of nuclear power plants Generations of BWRs gen II gen III gen III+ ABWR ESBWR Generation I Early Prototype Reactors - Shippingport - Dresden, Fermi I - Magnox Generation II Commercial Power Reactors - LWR-PWR, BWR - CANDU - VVER/RBMK Generation III Advanced LWRs - ABWR - System AP600 - EPR Generation III+ Evolutionary Designs Offering Improved Economics ABWR AP1000 ESBWR EPR HTRPM Generation IV - Highly Economical - Enhanced Safety - Minimal Waste - Proliferation Resistant Gen I Gen II Gen III Gen IV Overview of modern NPPs ABWR ABWR EPR AP1000 ESBWR HTR-PM Type BWR PWR PWR BWR HTR Vermogen In gebruik In aanbouw (voor 3/11) Respijtperiode 72 uur 30 min. 72 uur 24 uur Kernsmeltfrequentie (1/jaar) core catcher nee ja <24 uur <24 uur onnodig Technische levensduur (jr) ? Four units in service in Japan Manufacturers Toshiba or GE/Hitachi Experience was a major plus for the South Texas Project However, 1997 certified design did not allow for Digital instrumentation and Control Aircraft impact assessment Other requirements after 9/11 Amendments to original design Currently no new customers 53 54

10 AP1000 AP1000 Manufacturer Westinghouse Passive approach to cooling systems NRC final design certification in 2005 Four units under construction in China in Sanmen and Haiyang Technology transfer: Primary components of reactors 3+4 build in China Six active projects (6x2 reactors) in US, of which Vogtle-3, -4 and Summer-2,-3 are most likely to be build first Two steam generators Two hot legs and four cold legs (and four main coolant pumps) Fewer components and less piping Advanced Passively PWR (AP-1000) Passively cooled containment EPR Manufacturer Areva Four steam generators Four times redundant engineered safety systems Two active projects in US Two units under construction in Europe, two in China Technology transfer: primary components for Taishan 2 build in China Ground leveling for Taishan-3 and

11 European Pressurized Water Reactor Reactor building Turbine building Structural resistance EPR 4 veiligheidsgebouwen 4 x 100% Passively cooled core catcher Cooling water ESBWR HTR-PM Manufacturer GE/Hitachi Natural recirculation of the primary water flow Completely reviewed from scratch One project in the US, none elsewhere Demonstration project in China Based on German experience and the HTR-10 Inherent safety characteristics Water ingress scenarios possible 65 66

12 HTR-PM HTR-PM HTR-PM TRISO coated fuel particles Source: INET Fuel pebble with TRISO particles Conclusions 1. Majority of new build projects focuses on PWRs 2. Generation-III designs available with either more passive safety barriers or with more engineered safety barriers 3. HTR technology in demonstration phase and not yet commercial 4. More reactors available than presented here 1. APWR (PWR-Mitshubishi) 2. Kerena (BWR-Areva) 3. APR-1400 (PWR-Kopec) 71 72

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