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Indian nuclear reactor design
locations in India (14 IPHWR-220, 2 IPHWR - 540 and 3 IPHWR-700) and 13 more IPHWR-700 reactors planned or under construction. The IPHWR reactor is a horizontal
IPHWR
Indian nuclear reactor design
The IPHWR-220 (Indian Pressurized Heavy Water Reactor-220) is an Indian pressurized heavy-water reactor designed by the Bhabha Atomic Research Centre
IPHWR-220
Indian nuclear reactor design
connected to the grid on 10 January 2021. IPHWR, a class of Indian PHWRs. IPHWR-220, earlier lower power variant of IPHWR-700 CANDU, predecessor to Indian PHWR
IPHWR-700
Indian nuclear power plant
February 2014 to 15 September 2016 for a record number of 940 days. Two IPHWR units, each with a 700 MW capacity, are planned at this location. As of
Kaiga_Atomic_Power_Station
Indian atomic power plant
Manmohan Singh ministry approved outline plans to build two Indian-designed IPHWR-700 reactors, with two sister reactors a little later at Rajasthan Atomic
Kakrapar_Atomic_Power_Station
the commissioning of multiple IPHWR-700 and VVER-1000 reactors. India has commissioned 3 indigenous reactors of the IPHWR-700 design, 2 at Kakrapar and
Nuclear_power_in_India
Indian public sector undertaking
reactors like IPHWR-220, IPHWR-540, IPHWR-700, BWR-1, VVER 1000 reactors. Advanced heavy-water reactor BHAVINI Bhabha Atomic Research Centre IPHWR Nuclear power
Nuclear Power Corporation of India
Nuclear_Power_Corporation_of_India
Type of nuclear reactor
light water Organic medium Pressurized heavy-water reactor CANDU reactor IPHWR Han, Yuxuan; Zhong, Xianping (2024). "An overview of heavy water reactors"
Heavy-water_reactor
Type of nuclear fission reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Small_modular_reactor
Indian nuclear reactor design
Bhabha Atomic Research Centre (BARC) in Mumbai. It is a derivative of the IPHWR-220 reactor with innovative safety features and economic benefits. It is a
Bharat_Small_Modular_Reactor
Nuclear reactor design
heavy water reactor CANDU reactor: The predominant type of PHWR IPHWR-700 and IPHWR-220, PHWR types developed in India List of nuclear reactors Pressurized
Pressurized heavy-water reactor
Pressurized_heavy-water_reactor
Indian nuclear power plant
reactors, each a pressurized heavy-water reactor (PHWR) capable of producing 220 MW of electricity. Commercial operation of NAPS-1 began on 1 January 1991
Narora_Atomic_Power_Station
Device for controlled nuclear reactions
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Nuclear_reactor
Very small nuclear reactor of 1-20 MW capacity
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Nuclear_microreactor
Type of nuclear reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Graphite-moderated_reactor
Type of Soviet nuclear power reactor
contemporary western reactors. Similarly to CANDU reactors and the Indian IPHWR reactors it could be produced without the specialized industry required
RBMK
Small modular nuclear reactor design
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
BWRX-300
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Light_water_graphite_reactor
Nuclear research facility in Mumbai, India
The IPHWR class was developed from the CANDU reactors built at RAPS in Rawatbhata, Rajasthan. As of 2020, three successively larger designs IPHWR-220, IPHWR-540
Bhabha_Atomic_Research_Centre
Planned class of Ballistic missile submarines
Nuclear reactors Three-stage nuclear power programme PHWR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 FBR FBR-600 FBTR PFBR Thorium AHWR-300 Light water reactors
S5-class_submarine
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Lists_of_nuclear_reactors
Indian Nuclear power plant
Deuterium Uranium) pressurised heavy water reactor (PHWR) capable of producing 220 MW of electricity each. Ten years later, in 1973 RAPS-1 was put into service
Rajasthan Atomic Power Station
Rajasthan_Atomic_Power_Station
Class of Indian nuclear-powered ballistic missile submarines
Nuclear reactors Three-stage nuclear power programme PHWR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 FBR FBR-600 FBTR PFBR Thorium AHWR-300 Light water reactors
Arihant-class_submarine
First industrial-scale reactor in the Soviet Union
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
A-1_(nuclear_reactor)
Canadian heavy water nuclear reactor design
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
CANDU_reactor
Nuclear fission reactor family
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
KLT-40_reactor
Plant in Polyarnye Zori, Russia on the Kola Peninsula
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Kola_Nuclear_Power_Plant
Nuclear reactor design
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Economic Simplified Boiling Water Reactor
Economic_Simplified_Boiling_Water_Reactor
India's nuclear energy programme envisioned by Homi J. Bhabha
220 MWe, 540 MWe and 700 MWe capacity under the designations IPHWR-220, IPHWR-540 and IPHWR-700 respectively. Indian uranium reserves are capable of generating
India's three-stage nuclear power programme
India's_three-stage_nuclear_power_programme
Naturally occurring uranium self-sustaining nuclear chain reactions
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Natural nuclear fission reactor
Natural_nuclear_fission_reactor
Chinese small modular nuclear reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
HTR-PM
Type of nuclear reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
UNGG_reactor
Indian nuclear reactor design
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Advanced_heavy-water_reactor
Type of nuclear reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Pressurized_water_reactor
Nuclear fuel that has been irradiated in a nuclear reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Spent_nuclear_fuel
Nuclear reactor design
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Advanced boiling water reactor
Advanced_boiling_water_reactor
Prototype pebble bed reactor, China
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
HTR-10
Chemical compound
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
FLiBe
Type of nuclear fission reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Traveling_wave_reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
List of commercial nuclear reactors
List_of_commercial_nuclear_reactors
Russian nuclear reactor design based on the RBMK reactor design
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
MKER
New nuclear reactor technologies under development
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Generation_IV_reactor
Nuclear fission reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
OK-650_reactor
Russian small nuclear reactor design
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
EGP-6
Nuclear reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
RITM-200
Nuclear reactor where water boils in core
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Boiling_water_reactor
Type of nuclear reactor cooled by molten sodium
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Sodium-cooled_fast_reactor
American nuclear power plant
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
AP1000
Fast neutron research reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
MBIR
Proposed nuclear reactor design
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Energy_Multiplier_Module
French nuclear reactor type
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
N4_(nuclear_reactor)
Nuclear reactor generating more fissile material than it consumes
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Breeder_reactor
Russian fast breeder nuclear reactor, operating since 2016
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
BN-800_reactor
Nuclear reactor concept
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Clean and Environmentally Safe Advanced Reactor
Clean_and_Environmentally_Safe_Advanced_Reactor
Nuclear power plant design
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Integral_Molten_Salt_Reactor
Third-generation pressurised water nuclear reactor design
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
EPR_(nuclear_reactor)
U.S. project 1946–1961
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Aircraft_Nuclear_Propulsion
Chinese nuclear reactor design
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Hualong_One
South Korean advanced pressurized water nuclear reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
APR-1400
Nuclear reactor design
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
PRISM_(reactor)
Lead-cooled reactor family designed in Russia
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
BREST_(reactor)
Nuclear reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
KN-3_reactor
Type of nuclear reactor, CO2 or He cooled
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Gas-cooled_reactor
Soviet / Russian nuclear reactor type
(1812/2277/2349 psi) pressure respectively so that it does not boil at the normal (220 to over 320 °C [428 to >608°F]) operating temperatures. Water in the reactor
VVER
Soviet marine nuclear reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
OK-150_reactor
Russian nuclear fission reactor for use in submarines
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
BM-40A_reactor
Russian sodium-cooled fast breeder reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
BN-600_reactor
Nuclear power system
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Steam-Generating Heavy Water Reactor
Steam-Generating_Heavy_Water_Reactor
Small nuclear fission reactor for naval propulsion cooled by a liquid metal
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
VT-1_reactor
Type of nuclear reactor that uses normal water
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Light-water_reactor
Type of very-high-temperature reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Pebble-bed_reactor
Russian nuclear pressurized water reactors
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
VM_reactor
Proposed fission reactor design
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Fuji_Molten_Salt_Reactor
Type of nuclear reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Aqueous_homogeneous_reactor
South Korean nuclear reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
OPR-1000
Type of nuclear reactor that operates at high temperatures as part of normal operation
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
High-temperature gas-cooled reactor
High-temperature_gas-cooled_reactor
Nuclear power plant south of Chennai, India
constructed nuclear power station[citation needed], with two units each generating 220 MW of electricity. The first and second units of the station went critical
Madras_Atomic_Power_Station
Russian fast neutron research reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
BOR-60
Concept nuclear reactor whose water operates at supercritical pressure
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Supercritical_water_reactor
Type of nuclear reactor that uses molten material as fuel
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Liquid fluoride thorium reactor
Liquid_fluoride_thorium_reactor
Type of nuclear reactor cooled by heat pipes
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Heat_pipe-cooled_reactor
Nuclear reactor design
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Integral_fast_reactor
Indian nuclear reactor design
commonality of majority of non-nuclear island components of the design with the IPHWR-700 pressurized heavy-water reactors currently in use to limit design timelines
IPWR-900
Nuclear reactor where the coolant is liquid metal
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Liquid_metal_cooled_reactor
Nuclear power plant in Germany
for 220 kV and two for 110 kV. The circuits for 110 kV were mounted on the lowest of the three crossbars of the pylons, and the circuits for 220 kV on
Obrigheim_Nuclear_Power_Plant
Nuclear fission reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
OK-550_reactor
Nuclear reactor where fast neutrons maintain a fission chain reaction
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Fast-neutron_reactor
Molten salt reactor prototype
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
TMSR-LF1
Type of British nuclear reactor
efficiently, countering the thermal efficiency advantage. Like the magnox, CANDU, IPHWR, and RBMK reactors, and in contrast to light water reactors, AGRs are designed
Advanced_gas-cooled_reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
BN-Reactor
Proposed nuclear reactor currently undergoing development in the U.S.
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Small, sealed, transportable, autonomous reactor
Small,_sealed,_transportable,_autonomous_reactor
German nuclear reactor design proposal with liquid metal cooling loops
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Dual_fluid_reactor
Type of British nuclear reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Magnox
Nuclear reactor, Oak Ridge 1965–1969
page 10) "The MSRE was fueled with 39 kilograms of 233U that contained ~220 parts per million (ppm) of 232U [...that was bred in] various Light Water
Molten-Salt Reactor Experiment
Molten-Salt_Reactor_Experiment
Fast-neutron nuclear reactor cooled by molten lead
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Lead-cooled_fast_reactor
Molten salt reactor program
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
TMSR (Chinese reactor project)
TMSR_(Chinese_reactor_project)
Nuclear reprocessing plant in Russia
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Mayak
Experimental nuclear reactor
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Molten Salt Demonstration Reactor
Molten_Salt_Demonstration_Reactor
Breeder reactor in Tamil Nadu, India
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
Fast_Breeder_Test_Reactor
Proposed nuclear power plant design
D2O Pressurized CANDU CANDU 6 CANDU 9 EC6 AFCR ACR-1000 CVTR IPHWR IPHWR-220 IPHWR-540 IPHWR-700 PHWR KWU MZFR R3 R4 Marviken H2O HWLWR ATR HW BLWR 250
ThorCon_nuclear_reactor
travel, tourism, insurance
IPHWR 220
IPHWR 220
IPHWR 220
IPHWR 220
IPHWR 220
IPHWR 220
IPHWR 220
IPHWR 220
IPHWR 220
travel, tourism, insurance