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From IAEA TECDOC-1450 "Thorium Fuel Cycle – Potential Benefits and Challenges", Table 1: Thorium utilization in different experimental and power reactors.^[1] Additionally, Dresden 1 in the United States used "thorium oxide corner rods".^[2]

Name	Country	Reactor type	Power	Fuel	Operation period
AVR	Germany (West)	HTGR, experimental (pebble bed reactor)	15 MW(e)	Th+235 U Driver fuel, coated fuel particles, oxide & dicarbides	1967–1988
THTR-300	Germany (West)	HTGR, power (pebble type)	300 MW(e)	Th+235 U , Driver fuel, coated fuel particles, oxide & dicarbides	1985–1989
Lingen	Germany (West)	BWR irradiation-testing	60 MW(e)	Test fuel (Th,Pu)O₂ pellets	1968–1973
Dragon (OECD-Euratom)	UK (also Sweden, Norway and Switzerland)	HTGR, Experimental (pin-in-block design)	20 MWt	Th+235 U Driver fuel, coated fuel particles, oxide & dicarbides	1966–1973
Peach Bottom	United States	HTGR, Experimental (prismatic block)	40 MW(e)	Th+235 U Driver fuel, coated fuel particles, oxide & dicarbides	1966–1972
Fort St Vrain	United States	HTGR, Power (prismatic block)	330 MW(e)	Th+235 U Driver fuel, coated fuel particles, Dicarbide	1976–1989
MSRE ORNL	United States	MSR	7.5 MWt	233 U molten fluorides	1964–1969
BORAX-IV & Elk River Station	United States	BWR (pin assemblies)	2.4 MW(e); 24 MW(e)	Th+235 U Driver fuel oxide pellets	1963–1968
Shippingport	United States	LWBR, PWR, (pin assemblies)	100 MW(e)	Th+233 U Driver fuel, oxide pellets	1977–1982
Indian Point 1	United States	LWBR, PWR, (pin assemblies)	285 MW(e)	Th+233 U Driver fuel, oxide pellets	1962–1980
SUSPOP/KSTR KEMA	Netherlands	Aqueous homogenous suspension (pin assemblies)	1 MWt	Th+HEU, oxide pellets	1974–1977
NRX & NRU	Canada	MTR (pin assemblies)	20 MW; 200 MW (see)	Th+235 U , Test Fuel	1947 (NRX) + 1957 (NRU); Irradiation–testing of few fuel elements
CIRUS; DHRUVA; & KAMINI	India	MTR thermal	40 MWt; 100 MWt; 30 kWt (low power, research)	Al+233 U Driver fuel, ‘J’ rod of Th & ThO2, ‘J’ rod of ThO₂	1960–2010 (CIRUS); others in operation
KAPS 1 &2; KGS 1 & 2; RAPS 2, 3 & 4	India	PHWR, (pin assemblies)	220 MW(e)	ThO₂ pellets (for neutron flux flattening of initial core after start-up)	1980 (RAPS 2) +; continuing in all new PHWRs
FBTR	India	LMFBR, (pin assemblies)	40 MWt	ThO₂ blanket	1985; in operation
Petten	Netherlands	High Flux Reactor thorium molten salt experiment	45 MW(e)	?	2024; planned

References

^ "IAEA-TECDOC-1349 Potential of thorium-based fuel cycles to constrain plutonium and to reduce the long-lived waste toxicity" (PDF). International Atomic Energy Agency. 2002. Retrieved 2009-03-24.
^ Spent Nuclear Fuel Discharges from U. S. Reactors. Energy Information Administration. 1995 [1993]. p. 111. ISBN 978-0-7881-2070-1. Retrieved 11 June 2012. They were manufactured by General Electric (assembly code XDR07G) and later sent to the Savannah River Site for reprocessing.

[1] "IAEA-TECDOC-1349 Potential of thorium-based fuel cycles to constrain plutonium and to reduce the long-lived waste toxicity" (PDF). International Atomic Energy Agency. 2002. Retrieved 2009-03-24.

[2] Spent Nuclear Fuel Discharges from U. S. Reactors. Energy Information Administration. 1995 [1993]. p. 111. ISBN 978-0-7881-2070-1. Retrieved 11 June 2012. They were manufactured by General Electric (assembly code XDR07G) and later sent to the Savannah River Site for reprocessing.

[1]

[2]

See also

References