Presentation: Safety analysis of graphite core in molten salt test reactor

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Safety analysis of graphite core in molten salt test reactor Derek Tsang SINAP 16.09.2013

钍基熔盐核能系统


Introduction v  The Chinese Academy of Sciences (CAS) has launched a Thorium Molten Salt Reactor (TMSR) research project in 2011. v  350M USD for 5 years v  To develop generation IV molten salt reactors. v  Multipurpose applications of high temperature nuclear energy. v  To build two molten salt test reactors between 2015 and 2017. v  A CAS center for TMSR research has been set up at the Shanghai Institute of Applied Physics (SINAP) to lead the project.



•  SINAP has a light source: Shanghai Synchrotron Radiation Facility (SSRF) •  150 MeV Linear accelerator. •  3.5 GeV Booster, 180m circumference •  3.5 GeV Storage Ring, 432m circumference •  Number of Cells = 20


Introduction v  Two types of molten salt reactors: v  Molten salt and molten salt-cooled reactor.

v  Molten salt reactors use salt as fuel and coolant v  Molten salt-cooled reactors use TRISO fuel and salt as coolant only. v  Molten salt reactors may have a fully closed fuel cycle, however, online reprocessing is challenging. v  Molten salt-cooled reactors have a once-through fuel cycle, however, have high temperature and efficiency.


Molten salt coolant v  Coolant salt has v  Good thermal conductivity v  High boiling point v Nuclear system can operate at much lower pressure than high temperature gas cooled reactor

v  High melting point v Trap fission products in an accident

v  Large heat capacity v During accident the temperature of the core rises slowly


10MW salt-cooled test reactor v  TMSR SF1 v  Built around 2015~2016 v  Aims: v  To gain experiences on design, construction and operation v  To validate models, analyses and codes v  To test the equipment and safety features v  To accumulate operation data for larger-size reactors design and licensing


10MW salt-cooled test reactor v  TRISO is used as nuclear fuel v  6cm diameter fuel pebbles

v  Graphite is used as moderator and reflector v  Primary coolant is FLiBe salt v  Operating temperature is between 600°C and 650 °C v  Core dimensions is 2.6m(dia.) x 3.0m(h)


10MW salt-cooled test reactor


Challenges for the 10MW test reactor &  Reactor licensing Ø  No molten salt-cooled or molten salt reactor has been licensed in China before Ø  The regulators in China have limited exposure to either molten salt-cooled or molten salt reactor.

&  Stress analysis &  Material properties &  Irradiation data


Graphite stress analysis v  Density of graphite: 1.77g/cm3 v  Density of molten salt: 1.99g/cm3 v  Buoyant force acts on graphite bricks! v  Graphite bricks must be constrained within the core! v  Solid liquid interaction


Graphite problems v  Molten salt may penetrate into graphite. v  Modify graphite material properties?!? v  How to measure Young’s modulus with molten salt at high temperature: v  Dynamic method v  Static method


Graphite Irradiation program v  Measure irradiated graphite material properties v  Young’s modulus v  CTE v  Dimensional change v  Thermal conductivity v  Tensile strength v  Compressive strength

v  With and without molten salt.


Graphite experiments v  Shaking table 2m x 2m v  Seismic test on graphite component


Thank you!


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