MSR in Nederland. Jan Leen Kloosterman Rudy Konings TU-Delft Challenge the future. Delft University of Technology

MSR in Nederland 14-10-2014

Jan Leen Kloosterman Rudy Konings TU-Delft

Delft University of Technology

Challenge the future

Reactor Institute Delft Research on Energy and Health with Radiation Nuclear Energy & Radiation Applications

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Nuclear Energy & Radiation Applications

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Chemical labs


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Chemical labs TU Lab @ TU Delft Thorium Uranium


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Chemical Engineering


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Uranium isotopes Very stable, but not fissile

Less stable, but fissile  Good fuel

99,3%

0,7%


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Nuclear fission Radio-active

U  n  X  Y  n  200 MeV CH 4  2O 2  CO 2  2H 2 O  8eV

235


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neutron U-235

Moderator

U-235

U-238

U-239

Moderator

Np-239 October 14, 2014

Pu-239

U-238

Pu-239


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Fuel pellets Contain 4% Uranium-235 and 96% Uranium-238


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Nuclear fission Radio-active


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Decay heat production for Borssele (installed power1500 MW, decay power 100 MW)


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Temperature profile in PWR fuel pin


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Temperature effects in PWR fuel pin


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Huidige Reactoren • Hoge druk (75-150 bar) • Slecht geleidende splijtstof in een huls van sterk oxiderende materiaal (T>1000 0C) • Veel gestapelde veiligheidssystemen • Veel stappen in splijtstofcyclus (fabricage, transport, opwerking, recycling, etc) • Inefficient splijtstofgebruik (1% uranium) • Langlevend kernafval


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Fast reactors


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neutron U-235

Moderator

U-235

U-238

Pu-239

Moderator

U-238

Pu-239


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Fast neutron U-235

U-238 U-235 Pu-239 U-238

Pu-239

Pu-239


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Fast neutron Pu-239

U-238 U-238 Pu-239

Pu-239

With no moderator, plutonium gives more neutrons !

Pu-239 U-238 U-238 Pu-239

Pu-239

Pu-239


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Fast reactors

Phenix (F)

Monju (Jp)

Super-Phenix (F)

BN-600 (R)

PFBR (I)

CEFR (C)


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Fuel Cycle LWR-FR

LWR 200.000 a

500 aa 5.000 Pu+Am

FR

500 a

Renewable Energy, SepNuclear 27, 2011 Energy & Radiation Applications

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Snelle Reactoren • Vloeibare metalen als koelmiddel. Extra veiligheidsmaatregelen nodig. • Meer nawarmte dan bij LWR (ook bij versnellergedreven systemen!) • Vervorming van splijtstof gevaarlijk! • Veel stappen in splijtstofcyclus (fabricage, transport, opwerking, recycling, etc) • 50 jaar geleden gekozen voor LMFBR in plaats van MSR. Nu wel de goede keuze maken! Nuclear Energy & Radiation Applications

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Fuel cycle MSR Thorium

Splijtingsproducten


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Breeding with thorium U-233

Moderator

Th232

U-233

U-233


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Voordelen MSR • Homogeen medium voor splijtstof en koelmiddelgeen temperatuurgradienten • Continue zuivering en controle van het zoutgeen splijtstoffabricage, transport, etc. • Uitzetting zout geeft extra negatieve terugkoppeling • Lang-levende stoffen (actiniden) blijven in het zout totdat ze verspleten zijn. • Bij ongevallen splijtstof in veilige toestand • Primaire en secundaire systeem drukloos Nuclear Energy & Radiation Applications

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Voordelen MSR • Homogeen medium voor splijtstof en koelmiddelgeen temperatuurgradienten • Continue zuivering en controle van het zoutgeen splijtstoffabricage, transport, etc. Paradigma verschuiving: • Uitzetting zoutkrampachtig geeft extradenegatieve In plaats van splijtstof niet te vervormen en te blijven koelen, laat je het stromen terugkoppeling veilige opslag. • Lang-levendenaar stoffen (actiniden) blijven in het zout totdat ze verspleten zijn. • Bij ongevallen splijtstof in veilige toestand • Primaire en secundaire systeem drukloos Nuclear Energy & Radiation Applications

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USA: Transatomic Power


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USA: Transatomic Power


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China: TMSR


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China: TMSR


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China: TMSR

MSRE, Oak Ridge, 1965-1969


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Canada: Terrestrial Energy Integrated Molten Salt Reactor


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Europe: Molten Salt Fast Reactor


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MSR/thorium research @ 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).


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TU Delft: RESTORE & MASTER Restore knowledge from the past to master it for the future RESTORE: Research Thorium Reactor MASTER: Molten Actinide Salt Thorium Energy Reactor


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TU Delft: RESTORE & MASTER

RESTORE: • Research Thorium Reactor • Similar to Oak Ridge MSRE • Low power < 10 MWth • Helium bubbling • No salt cleaning • Thermal neutron spectrum • Graphite moderated • Operation with enriched uranium • Operation with plutonium • Experiments with thorium


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MASTER: • Molten-Actinide Salt Thorium Energy Reactor • Medium power ≈1000-2000 MWth • Helium bubbling to extract gaseous FP and noble metals • Salt cleaning by fluorination and reductive extraction processes • Operation with uranium and plutonium • Operation with thorium fuel cycle Nuclear Energy & Radiation Applications

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Planning RESTORE and MASTER Costs (million €)

Time (a) 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22

Research thorium reactor (RESTORE) Knowledge and expertise buildup Conceptual design RESTORE Detailed design RESTORE Licensing RESTORE Construction RESTORE

60 60 60 20 500 700

Molten salt thorium energy reactor (MASTER) Conceptual design Detailed design Licensing Construction

MASTER MASTER MASTER MASTER


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TU Delft: RESTORE & MASTER 1. physical and chemical properties of the salts to be used 2. thermo-hydraulics properties of the salts to be used. 3. structural materials (Hasteloy-N and others) 4. graphite behaviour under irradiation conditions 5. chemical interaction between salt and materials 6. ex-core experimental loops with molten salts 7. in-core experimental loops with molten salts 8. transient initiators 9. safety evaluation. 10. fuel clean up scheme


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# neutrons per absorption

Number of neutrons per absorption

Thermal breeding

Fast breeding 239Pu

233U

Breeding

Chain reaction

neutron energy / eV Nuclear Energy & Radiation Applications

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MSR in Nederland. Jan Leen Kloosterman Rudy Konings TU-Delft Challenge the future. Delft University of Technology

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