Research and development
Thorium can be used now, but at the same time research for its commercial use is still going on. Some very safe processes are being developped, like Molten Salt Reactors or Accelerator Driven Systems.
- The reuse of current U-235 based reactors, by replacing the U-238 blanket by Th-232 blanket. This could be done in Belgium too as demonstrated by the nuclear study center of Mol (SCK-CEN).
- The Pebble Bed Reactors, where fissile (U-233) and fertile products (Th-232) are encapsulated in pebbles of the size of a tennis ball.
- The Molten Salt Reactors, where Thorium is smelted in a liquid salt circulating in the reactor.
- The Accelerator Driven Systems, where the neutrons are produced by an accelerator and no U-233 (or other fissile products) blanket is necessary to initiate the fission reaction.
The 6 nuclear technologies listed below have been selected by the World Nuclear Association to develop safe “Generation IV Nuclear Reactors” (in red = EU projects). Some of them are already identified as able to burn Thorium.
|
Type of reactor |
Coolant |
Projects? |
Use of Thorium? |
|
Gas-cooled
fast |
helium |
· Allegro, 75 MWt demo GFR (EU-project run by
CEA+Czech, Hungary, Slovakia and Poland) · Energy Multiplier Module (EM²), 500
MWt (General Atomics (GA)) |
? |
|
Lead-cooled fast reactors |
lead or Pb-Bi |
· SVBR-100 & BREST-300 (Russia) · ALFRED 300 MWt (EU-project in Romania) · MYRRHA (EU-project in Belgium) · LFR, pilot plant reactor (Westinghouse by 2021) |
YES “can use depleted U or Th fuel
matrices” |
|
Molten salt fast |
Fluoride salts |
· TAP
MSR (US private project by Transatomic Power
Corporation) |
YES “will take in Th fuel cycle, |
|
Molten
salt reactor - Advanced High- |
Fluoride salts |
· TMSR Research Centre, small solid- fuel
prototype (SINAP, under China Academy of Sciences / operation in 2015) |
? |
|
Sodium-cooled fast reactors |
sodium |
· BN-800 at Beloyarsk in Russia (operations
started in 2014 but not grid- connected by mid-2015) · PFBR Kalpakkam of 500 MWe in India (late 2015) · Astrid sodium-cooled fast reactor SFR
(EU-project in France) |
? |
|
Supercritical water-cooled reactors |
water |
· ? |
? |
|
Very high temperature gas |
helium |
· prismatic
blocks’ core : HTTR (Japan) & GTMHR (General Atomics) · pebble
bed’s
core : HTR-PM,
demo unit (China, Shidaowan,
under construction in 2015) |
YES has been used in German Th-Pebble bed
reactor THTR300 |