Thorium in de Gesmolten Zout Reactor
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1 Thorium in de Gesmolten Zout Reactor Jan Leen Kloosterman TU-Delft Delft University of Technology Challenge the future Reactor Institute Delft Research on Energy and Health with Radiation 2 1
2 3 Research Themes (1) Energy solar cells batteries }Materials research hydrogen storage nuclear reactors 4 2
3 Research Themes (2) Health radiation and radioactive nuclides for therapy radiation and radioactive nuclides for diagnostics radiation detection systems for imaging new production routes for radionuclides 5 Simeon de pilaarheilige, Simeon Stylites, Carel Willink,
4 World population 11 billion population / million year 8 World population and energy use Country Population (million) Electricity (kwh/cap) World OECD China Asia Africa Energy (Mtoe/cap) IEA, Key world energy statistics, 2013 data from
5 Energy demand by region WEO CO2 concentration CO 2 in 2100 (with business as usual) Double pre-industrial CO CO 2 now CO 2 concentration (ppm) 10 Last 160,000 years (from ice cores) and the next 100 years Temperature difference from now C Now 11 Time (thousands of years) Source: IPCC 5
6 Physics of Nuclear Energy 13 Elements, atoms and more Atoms Electrons Protons Neutrons 14 6
7 Uranium isotopes Very stable, but not fissile Less stable, but fissile Good fuel 99,3% 0,7% 15 Nuclear fission Radio-active U n X Y n 200 MeV CH 2O CO 2H O 8eV
8 Fossils equivalent to 1 gram of U235 Gasoline Coal 2500 liter 3000 kg 17 Moderation and Enrichment 20 8
9 Moderation 21 Enrichment by Centrifuge 96% U-238 5% U % U % U-235 Cascade of ultracentrifuges 23 9
10 neutron U-235 Moderator U-238 U-235 U-239 Moderator Np-239 U-238 Pu-239 January 30, Pu Nuclear Power Plants UVA, March 16, 2011 vision from
11 Pressurized Water Reactor 27 Fuel pellets Contain 4% Uranium-235 and 96% Uranium
12 Boiling Water Reactor 30 Feedback coefficients U-235 Moderator Moderator feedback Doppler feedback U-238 U-235 1) Stable system Pu-239 2) Loss of coolant stops fission chain reaction 3) Loss of moderation stops fission chain reaction 33 12
13 Vervalwarmte productie 34 Containments nuclear power plant Fuel rod Primary system (steel) Containments (2x concrete+steel) 38 13
14 Nuclear waste production 41 U-235 Moderator U-238 U-235 Higher actinides Pu Am Fission products 42 14
15 Radiotoxicity of LWR spent fuel Actinides Fiss Prods Ore Radiotoxicity (Sv) Storage time (a)
16 Thorium in MSR or LFTR Thorium Fission products 52 Breeding with thorium U-233 Moderator Th232 U-233 Pa233 U
17 Radiotoxicity of LWR spent fuel Actinides Fiss Prods Ore Radiotoxicity (Sv) Storage time (a) 54 Radiotoxicity of MSR 55 17
18 Fuel cycle MSR Thorium Splijtingsproducten 58 Heat Transfer Reactor Experiments 1 and 2 (1956) HTRE-1 (20 MWth) 59 18
19 Heat Transfer Reactor Experiment 3 ( ) HTRE-3 (30 MWth) 60 Hangar Aircraft Nuclear Propulsion program, Idaho 61 19
20 Molten Salt Reactor Experiment (MSRE) China: TMSR 63 20
21 USA: Transatomic Power 64 Canada: Terrestrial Energy 65 21
22 Europe: Molten Salt Fast Reactor 66 MSFR Reactor design parameters Working parameters: High temperature (750 0 C) Low pressure (1 bar) Circulation time (4 sec) LiF-ThF4-UF4-(TRU)F3 ( mol%). Online processing / fueling Three loops 67 22
23 MSR/thorium TU Delft D.J. Journée, Helium bubbling in a Molten Salt Fast Reactor, A flotation process, Delft (2014). Chris Graafland, Modeling and analysis of a depressurized loss of forced cooling event in a thorium fueled high temperature reactor, Delft (2014). L.L.W. Frima, Burnup in a Molten Salt Fast Reactor, Delft (2013). R. van Bremen, Water ingress scenario analyses of a thorium fuelled HTR, Delft (2013). K. Nagy, Dynamics and Fuel Cycle Analysis of a Moderated Molten Salt Reactor, Delft (2012). D.A. Rodriguez Sanchez, Safety analysis of a thorium-fueled High Temperature Gas-cooled Reactor, Delft (2012). E. van der Linden, Coupled Neutronics and Computational Fluid Dynamics for the Molten Salt Fast Reactor, Delft (2012). Jacques Verrue, Ding Ming and Jan Leen Kloosterman, Thorium utilization in a small and long-life HTR, Delft (2011). R.J.S. van't Eind, Simulation of Fast Molten Salt Reactor, Delft (2011). F. de Vogel, Parametric Studies on the Moderation Ratio of a 2-zone 1-fluid Molten Salt Reactor, Delft (2011). M.W. Hoogmoed, Sensitivity and Uncertainty Analysis for the Thorium Molten Salt Reactor using the SCALE and ERANOS Code Systems, Internship Grenoble (2010). M.W. Hoogmoed, A Coupled Calculation Code System for the Thorium Molten Salt Reactor, Delft (2009). G. Rodigari, Application of the Adjoint Sensitivity Analysis to the Delayed Neutron Parameters in a Molten Salt Reactor, Delft (2008). 68 TU Delft: RESTORE & MASTER RESTORE: Research Thorium Reactor Similar to Oak Ridge MSRE Low power < 10 MWth Helium bubbling No further salt cleaning Thermal neutron spectrum Graphite moderated Operation with enriched uranium Conversion of thorium to U
24 TU Delft: RESTORE & MASTER MASTER: Molten-Actinide Salt Thorium Energy Reactor Medium power 1000 MWth Helium bubbling to extract GFP and noble metals Salt cleaning by fluorination and reductive extraction processes Operation with thorium breeder fuel cycle 70 Conclusions A Molten Salt Reactor (MSR) has a completely new safety philosophy: let the fuel expand and flow! The Molten Salt Reactor contains no volatile fission products The Molten Salt Reactor can recycle plutonium and americium of other reactors Thorium in a MSR produces much less long-lived nuclear waste Thorium in a MSR can produce all electricity consumed worldwide for many tens of thousands of years 71 24
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