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Nuclear reactor in Fujian province, China
The CFR-600 (Xiapu fast reactor pilot project) is a sodium-cooled pool-type fast-neutron nuclear reactor in Xiapu County, Fujian province, China, on Changbiao
CFR-600
primary reactor type, with a planned 1400 GWe capacity by 2100, and with the CFR-600 China's Thorium Molten Salt Reactor project aims to utilize the thorium
Nuclear_power_in_China
Small modular nuclear reactor design
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
BWRX-300
Very small nuclear reactor of 1-20 MW capacity
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Nuclear_microreactor
Type of nuclear reactor cooled by molten sodium
commercial SFRs are under construction as of 2026,[update] including a CFR-600 in China and the Natrium and Aurora reactors in the United States. The
Sodium-cooled_fast_reactor
License
a biologic product into interstate commerce (21 CFR 601.2). The BLA is regulated under 21 CFR 600 – 680. A BLA is submitted by any legal person or entity
Biologics_license_application
Nuclear reactor where fast neutrons maintain a fission chain reaction
March 2024. CFR-600, China's 600 MWe Experimental Fast Reactor (CEFR) (experimental) and CFR‑600 (under construction at Xiapu / Fu’an) — CFR‑600 intended
Fast-neutron_reactor
Nuclear reactor where the coolant is liquid metal
Publishing Company. Retrieved 2026-06-09. "Fuel despatched for China's CFR-600 fast neutron reactor". Archived from the original on 4 January 2025. "Russia
Liquid_metal_cooled_reactor
Type of nuclear reactor
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Heavy-water_reactor
Nuclear reactor where water boils in core
concept, known as the simplified boiling water reactor (SBWR). This smaller 600 megawatt electrical reactor was notable for its incorporation—for the first
Boiling_water_reactor
Russian sodium-cooled fast breeder reactor
The BN-600 reactor is a sodium-cooled fast breeder reactor, built at the Beloyarsk Nuclear Power Station, in Zarechny, Sverdlovsk Oblast, Russia. It has
BN-600_reactor
New nuclear reactor technologies under development
two largest experimental sodium cooled fast reactors are in Russia, the BN-600 and the BN-800 (880 MWe gross). These NPPs are being used to provide operating
Generation_IV_reactor
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Lists_of_nuclear_reactors
Naturally occurring uranium self-sustaining nuclear chain reactions
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Natural nuclear fission reactor
Natural_nuclear_fission_reactor
Indian fast breeder nuclear reactor design
The Fast Breeder Reactor-600 (FBR-600) or Indian Fast Breeder Reactor (IFBR) or Commercial Fast Breeder Reactor (CFBR) is a 600-MWe fast breeder nuclear
FBR-600
Nuclear reactor generating more fissile material than it consumes
only two commercially operating breeder reactors as of 2017[update]: the BN-600 reactor, at 560 MWe, and the BN-800 reactor, at 880 MWe. Both are Russian
Breeder_reactor
Type of nuclear reactor
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Graphite-moderated_reactor
Nuclear fission reactor
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
OK-650_reactor
Series of ratings assigned to different segments of automotive vehicles
Safety. Retrieved 24 March 2019. "40 CFR 600.315-08 - Classes of comparable automobiles. - Content Details - CFR-2011-title40-vol30-sec600-315-08". www
Vehicle_size_class
Nuclear reactor
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
RITM-200
Type of nuclear reactor
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Pressurized_water_reactor
Nuclear fuel that has been irradiated in a nuclear reactor
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Spent_nuclear_fuel
Chinese small modular nuclear reactor
An updated larger power plant, HTR-PM600, is planned with a capacity of 600 MWe using six HTR-PM reactor units. Nuclear power in China "China starts
HTR-PM
17 August 2015. Retrieved 16 August 2015. "China starts building second CFR-600 fast reactor: New Nuclear – World Nuclear News". world-nuclear-news.org
List of commercial nuclear reactors
List_of_commercial_nuclear_reactors
U.S. investigation into Russian interference in U.S. elections
directly from the investigation" and any other matters within the scope of 28 CFR 600.4 – Jurisdiction. The investigation's broad scope allowed Mueller to investigate
Mueller special counsel investigation
Mueller_special_counsel_investigation
Type of nuclear reactor cooled by heat pipes
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Heat_pipe-cooled_reactor
U.S. project 1946–1961
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Aircraft_Nuclear_Propulsion
Russian nuclear pressurized water reactors
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
VM_reactor
Soviet / Russian nuclear reactor type
increase in reactivity. The VVER-S-600 is to have a design life of 80 years. The estimated breeding ratio of the VVER-S-600 is 0.7 to 0.8, compared to 0.35
VVER
Russian fast breeder nuclear reactor, operating since 2016
mechanical properties, very similar to the BN-600 reactor core, but the fuel composition is not. While BN-600 uses medium-enriched uranium dioxide, this
BN-800_reactor
Nuclear fission reactor family
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
KLT-40_reactor
Molten salt reactor prototype
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
TMSR-LF1
Type of nuclear reactor that operates at high temperatures as part of normal operation
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
High-temperature gas-cooled reactor
High-temperature_gas-cooled_reactor
Nuclear fission reactor
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
OK-550_reactor
Nuclear reactor design
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Pressurized heavy-water reactor
Pressurized_heavy-water_reactor
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Light_water_graphite_reactor
Soviet marine nuclear reactor
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
OK-150_reactor
Nuclear reactor
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
KN-3_reactor
First industrial-scale reactor in the Soviet Union
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
A-1_(nuclear_reactor)
Nuclear reactor design
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
PRISM_(reactor)
Russian small nuclear reactor design
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
EGP-6
CFR Title 49, Parts 600 thru 699 - Federal Transit Administration (FTA) is one of twelve chapters comprising the United States Code of Federal Regulations
Title_49_CFR_Part_600_-_699
Small nuclear fission reactor for naval propulsion cooled by a liquid metal
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
VT-1_reactor
Type of nuclear fission reactor
resulted in the development of two 600 MW LWRs, the General Electric ABWR and later SBWR, and the Westinghouse AP-600 designs. However, these were later
Small_modular_reactor
Type of nuclear reactor
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
UNGG_reactor
Indian nuclear reactor design
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
IPHWR-700
Type of Soviet nuclear power reactor
being the active length. The maximum allowed temperature of a fuel rod is 600 °C. The fuel assemblies consist of two sets ("sub-assemblies") with 18 fuel
RBMK
Chinese nuclear reactor design
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Hualong_One
Russian nuclear fission reactor for use in submarines
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
BM-40A_reactor
Nuclear reprocessing plant in Russia
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Mayak
Lead-cooled reactor family designed in Russia
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
BREST_(reactor)
Type of nuclear reactor, CO2 or He cooled
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Gas-cooled_reactor
Nuclear reactor in China
Energy (CIAE) denied that any accident had occurred. Nuclear power in China CFR-600 "Criticality for China's first fast reactor". Nuclear Engineering International
China Experimental Fast Reactor
China_Experimental_Fast_Reactor
American Ultra-High Temperature Reactor Experiment (1959–1971)
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
UHTREX
Chinese nuclear reactor design
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
CPR-1000
Nuclear power safety method that does not require electrical power nor intervention
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Passive_nuclear_safety
Canadian heavy water nuclear reactor design
multi-reactor installations in large plants, and the optimized CANDU 6 in the 600 MWe class that is designed to be used in single stand-alone units or in small
CANDU_reactor
Nuclear reactor design
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Economic Simplified Boiling Water Reactor
Economic_Simplified_Boiling_Water_Reactor
Device for controlled nuclear reactions
plant. Sodium-cooled Most LMFBRs are of this type. The TOPAZ, BN-350 and BN-600 in the USSR; Superphénix in France; and Fermi-I in the United States were
Nuclear_reactor
Proposed nuclear reactor design
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Energy_Multiplier_Module
Categorisation of cars according to vehicle regulations or market segments
of the European Communities. 17 March 1999. Retrieved 12 July 2021. 40 CFR 600.315-08 "Terms and definitions of motor vehicles, trailers and combination
Car_classification
Topics referred to by the same term
CZ-550 action CFR-600, a sodium-cooled pool-type fast-neutron nuclear reactor under construction in Xiapu County, Fujian FBR-600, a 600-MWe fast breeder
600_(disambiguation)
South Korean advanced pressurized water nuclear reactor
improves resistance to stress corrosion cracking compared to the Inconel 600 used in prior designs. Like the late-evolution System 80+ design, the steam
APR-1400
Indian nuclear reactor design
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
IPHWR
Indian nuclear reactor design
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
IPWR-900
Type of nuclear reactor that uses normal water
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Light-water_reactor
American nuclear power plant
passively cooled containment initially led to the AP600 concept, with a smaller 600 to 700 MWe output, but this saw limited interest. In order to compete with
AP1000
Proposed nuclear power plant design
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
ThorCon_nuclear_reactor
Proposed nuclear reactor currently undergoing development in the U.S.
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Small, sealed, transportable, autonomous reactor
Small,_sealed,_transportable,_autonomous_reactor
German nuclear reactor design proposal with liquid metal cooling loops
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Dual_fluid_reactor
American highway driving fuel economy test series
save for the end of the test. The HWFET driving cycle is defined in 40 CFR 600.I. Soon after the federal government began emissions and fuel economy testing
HWFET
Molten salt reactor program
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
TMSR (Chinese reactor project)
TMSR_(Chinese_reactor_project)
Prototype pebble bed reactor, China
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
HTR-10
Fast-neutron nuclear reactor cooled by molten lead
The reactor outlet coolant temperature is typically in the range of 500 to 600 °C, possibly ranging over 800 °C with advanced materials for later designs
Lead-cooled_fast_reactor
Indian nuclear reactor design
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
IPHWR-220
Indian nuclear reactor design
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Advanced_heavy-water_reactor
Third-generation pressurised water nuclear reactor design
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
EPR_(nuclear_reactor)
2011 book by Hassan Rowhani
Hope (in Persian). Tehran, Iran: Center for Strategic Research. ISBN 978-600-290-023-4. Hassan Rowhani, Iran's moderate conservative behind nuclear breakthrough
National Security and Nuclear Diplomacy
National_Security_and_Nuclear_Diplomacy
South Korean nuclear reactor
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
OPR-1000
Chemical compound
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
FLiBe
Type of nuclear power reactor
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Reduced moderation water reactor
Reduced_moderation_water_reactor
Nuclear power plant design
fuel utilization. IMSR provides final heat at temperatures of around 550–600 °C, which results in an efficiency in the 44–45% range. Terrestrial Energy
Integral_Molten_Salt_Reactor
Fast neutron research reactor
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
MBIR
Nuclear power system
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Steam-Generating Heavy Water Reactor
Steam-Generating_Heavy_Water_Reactor
Russian fast neutron research reactor
BOR-60 reactor was constructed to perform tests for the commercial BN-350, BN-600 and BN-800 reactors, which also use fast neutron breeding. Construction began
BOR-60
Breeder reactor in Tamil Nadu, India
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Fast_Breeder_Test_Reactor
US lawyer used to avoid a conflict of interest
remain in effect in the Code of Federal Regulations, Title 28, part 600 (28 CFR §600). The regulations restrict the power to fire the special counsel into
Special_counsel
Type of nuclear fission reactor
of understanding to jointly develop a TWR. TerraPower planned to build a 600 MWe demonstration Plant, the TWR-P, by 2018 to 2022 followed by larger commercial
Traveling_wave_reactor
Former US government office
The provisions were replaced by Department of Justice regulation 28 CFR Part 600, which created the successor office of special counsel. The current regulations
United States Department of Justice Office of Special Counsel
United_States_Department_of_Justice_Office_of_Special_Counsel
Type of nuclear reactor
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Aqueous_homogeneous_reactor
Plant in Polyarnye Zori, Russia on the Kola Peninsula
June 2008, after further reviews, inspections and upgrade work. Four VVER-S-600 units are planned for the Kola II NPP which is to be located a few kilometres
Kola_Nuclear_Power_Plant
Type of British nuclear reactor
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Advanced_gas-cooled_reactor
Type of very-high-temperature reactor
costs for AVR dismantling without consideration of the vessel dismantling at 600 million € ( $750 million, which corresponded to 0.4 € ($0.55) per kWh of
Pebble-bed_reactor
Decommissioned nuclear reactor experiment in Idaho
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Organic Moderated Reactor Experiment
Organic_Moderated_Reactor_Experiment
US/Russian design concept ~1997 - never built
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Gas turbine modular helium reactor
Gas_turbine_modular_helium_reactor
26°48′13″N 120°09′18″E / 26.80361°N 120.15500°E / 26.80361; 120.15500 (CFR-600) Xudabao 4 4,400 2021 2028 China 40°21′05″N 120°32′47″E / 40.3514°N 120
List of nuclear power stations
List_of_nuclear_power_stations
Cars that are larger than a subcompact car but smaller than a mid-size car
of the European Communities. 17 March 1999. Retrieved 12 July 2021. 40 CFR 600.315-08 "Terms and definitions of motor vehicles, trailers and combination
Compact_car
Nuclear reactor, Oak Ridge 1965–1969
reactor (DFR) Generation IV Sodium (SFR) BN-350 BN-600 BN-800 BN-1200 CFR-600 Phénix Superphénix PFBR FBR-600 CEFR PFR PRISM Lead BREST-300 Helium gas (GFR)
Molten-Salt Reactor Experiment
Molten-Salt_Reactor_Experiment
Nuclear reactor design
of design variants have been considered, with power outputs varying from 600 to 1800 MWe. The most developed design variant is the ABWR-II, started in
Advanced boiling water reactor
Advanced_boiling_water_reactor
2019 U.S. government report on Russian interference in the 2016 election
then-Deputy Attorney General Rod Rosenstein appointed Robert Mueller, under 28 CFR § 600.1, as special counsel to take over and expand an existing FBI counterintelligence
Mueller_report
travel, tourism, insurance
CFR 600
CFR 600
Male
Norse
Old Norse name composed of the name of the fertility god Ing and the word úlfr "wolf," hence "Ing's wolf."
Male
Norse
Old Norse equivalent of Germanic Hrolf, HRÓLFR means "famous wolf."
Male
Scandinavian
Scandinavian form of Old Norse Óláfr, OLAF means "heir of the ancestors."
Male
Norse
Old Norse name composed of the elements gandr " staff, wand" or "fiend, monster" and álfr "elf," hence "fiendish elf" or "wand elf." In mythology, this is the name of a dwarf.
Surname or Lastname
English
English : habitational name from Critchlow in Lancashire, named from Celtic cr{u: _}g ‘hill’ + Old English hlÄw ‘mound’.
Male
Norwegian
Danish and Norwegian form of Old Norse Friðþjófr, FRIDTJOF means "peace-thief."
Male
Welsh
Medieval form of Welsh Caradoc, derived from the root car "love," CARADAWG means "dearly loved."
Male
Scandinavian
Scandinavian form of Old Norse Ingólfr, INGOLF means "Ing's wolf."
Male
Norse
Variant form of Old Norse Ãnleifr, ÓLÃFR means "heir of the ancestors."
Boy/Male
Celtic
Fighter.
Surname or Lastname
English (Yorkshire)
English (Yorkshire) : habitational name from Anlaby in Humberside, recorded 1234 as Anlaweby but in Domesday Book as Umloueby. The place is named with the Old Norse personal name Anláfr, Óláfr (see Oliff) + Old Norse býr ‘farm’, ‘settlement’.
Male
Scandinavian
Scandinavian form of Old Norse Friðþjófr, FRITJOF means "peace-thief."
Male
Norwegian
Danish and Norwegian form of Old Norse Friðþjófr, FRIDTHJOF means "peace-thief."
Male
Scandinavian
 Scandinavian form of Old Norse Hrólfr, ROLF means "famous wolf." Compare with other forms of Rolf.
Girl/Female
Biblical
The house of the lamb.
Boy/Male
Greek
Lordly.
Male
Icelandic
Icelandic form of Old Norse Óláfr, ÓLAFUR means "heir of the ancestors."
Male
Norwegian
Danish and Norwegian form of Old Norse Óláfr, OLAV means "heir of the ancestors."
Male
Norse
Old Norse name composed of the elements friðr "peace" and þjófr "thief," hence "peace-thief."
Male
Icelandic
Icelandic form of Old Norse Friðþjófr, FRIÃÞJÓFUR means "peace-thief."
CFR 600
CFR 600
CFR 600
CFR 600
CFR 600
CFR 600
CFR 600
travel, tourism, insurance