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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 |
