Coast Guard Depot Dates 2020, Meadow Knapweed Colorado, Hp Laserjet Pro Cp1025nw Color Printer, Coconut Water Mojito, Ice Cream Sundae Cookie Cups, 3rd Grade Science, " /> Coast Guard Depot Dates 2020, Meadow Knapweed Colorado, Hp Laserjet Pro Cp1025nw Color Printer, Coconut Water Mojito, Ice Cream Sundae Cookie Cups, 3rd Grade Science, "/> Coast Guard Depot Dates 2020, Meadow Knapweed Colorado, Hp Laserjet Pro Cp1025nw Color Printer, Coconut Water Mojito, Ice Cream Sundae Cookie Cups, 3rd Grade Science, " /> Coast Guard Depot Dates 2020, Meadow Knapweed Colorado, Hp Laserjet Pro Cp1025nw Color Printer, Coconut Water Mojito, Ice Cream Sundae Cookie Cups, 3rd Grade Science, "> Coast Guard Depot Dates 2020, Meadow Knapweed Colorado, Hp Laserjet Pro Cp1025nw Color Printer, Coconut Water Mojito, Ice Cream Sundae Cookie Cups, 3rd Grade Science, ">
 
t

Pool type sodium-cooled fast reactor (SFR) The sodium-cooled fast reactor ( SFR ) is a Generation IV reactor project to design an advanced fast neutron reactor . Prototype Fast Breeder Reactor The PFBR is a 500 MWe, sodium cooled, pool type, mixed oxide (MOX) fuelled reactor having two secondary loops. Unit ?0.46 ?MW ??? The ARC-100 is a 100 MWe sodium-cooled, fast flux, pool type reactor with metallic fuel. Schematic diagram showing the difference between the Loop … Accident afterheat exhausting system provided by the present invention, it has two characteristics, first independence.Independently heat-transfer system is overlapped by this system, and it has oneself a loop and secondary circuit (intermediate loop), can not rely on main heat-transfer system just the residue heat release of reactor core can be derived.It two is non-dynamic roles.One loop of this system and secondary circuit (intermediate loop) and the air that flows through air heat exchanger all adopt the mode of Natural Circulation to move, and in the trunk line of system, do not establish any valve, it is active having only the import and export air door of air heat exchanger, thereby has guaranteed the non-dynamic role of native system to greatest extent.In a word, native system effectively overcome the technology of enjoying defective, when accident conditions, can be effectively the residue heat release of reactor core be discharged. Image: ARC Nuclear. ?6 The Soviet BN-600 is sodium cooled. The Xiapu reactor will be a demonstration of that sodium-cooled pool-type fast reactor design. ?1.17 When accident conditionses such as the earthquake of fast reactor experience, system's power supply are all interrupted, all steam generators feedwater interruptions, the residue heat release of reactor core just can't pass through one, three loops derives.For successfully deriving residual heat of nuclear core, avoid core meltdown, an accident afterheat exhausting system must be set. Toward that end, an innovative hybrid loop-pool design for sodium cooled fast reactors (SFR) has been proposed (Zhao and Zhang, 2007). ?516 ?485 ? ?516 ??? Flow through the air themperature air heat exchanger intake air heat exchanger outlet of air heat exchanger A Sodium-cooled Fast Reactor (SFR) is a type of nuclear reactor that utilizes molten sodium metal as the reactor coolant as it allows for a high power density with a low coolant volume. System's thermal power The existing sodium cooled fast reactors (SFR) have two types of designs – loop type and pool type. 6. according to the accident afterheat exhausting system of claim 1,4 or 5 described pool type natrium cold fast reactors, it is characterized in that: described air heat exchanger (3) is provided with the chassis. The outlet of intermediate loop sodium temperature air heat exchanger entrance air heat exchanger The Chinese Experimental Fast Reactor (CEFR) is a 65MWt/20MWe sodium cooled fast reactor. 5. the accident afterheat exhausting system of pool type natrium cold fast reactor according to claim 4 is characterized in that: the import air door (4) of described air heat exchanger (3) and outlet air door (2) are provided with electronic and manual two kinds of drive units. Sodium-Cooled Fast Reactor (SFR) ... A large size (600 to 1 500 MW e) loop-type reactor with mixed uranium-plutonium oxide fuel and potentially minor actinides, supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors. One loop sodium flow ℃ A loop thermal power Among the figure, 1. pull out wind and smoke chimney, 2. air heat exchanger outlet air door, 3. air heat exchanger, 4. air heat exchanger import air door, 5. independent heat exchanger, 6. reactor vessel, 7. trunk line. This appendix describes analysis of a conceptual core design of a 2400 MWt sodium-cooled fast reactor with unity conversion ratio. 4. the accident afterheat exhausting system of pool type natrium cold fast reactor according to claim 1, it is characterized in that: described air heat exchanger (3) is a kind of non-active sodium-air heat exchanger. The reactor will use mixed-oxide (MOX) fuel with 100 GWd/t burnup, and will feature two coolant loops producing steam at 480°C. ?5 gross liquid sodium cooled, fast neutron spectrum reactor that uses U-10%Zr metallic fuel with HT-9 ferritic-martensitic stainless steel clad. The invention discloses an accidental afterheat discharge system of a pool type SFR. Disambiguation page providing links to topics that could be referred to by the same search term. Intermediate loop sodium flow 164, TOUGH2-06, pp. The Xiapu reactor will be a demonstration of that sodium-cooled pool-type fast reactor design. One loop sodium temperature independence heat exchanger entrance independence heat exchanger outlet ? The present invention is achieved in that a kind of accident afterheat exhausting system of pool type natrium cold fast reactor, and it is an independently heat transfer system, the loop of being made up of heat-exchange apparatus and corresponding pipeline and measurement, control instrument.Key is that described heat-exchange apparatus is to be connected in series by independent heat exchanger and air heat exchanger, and wherein the bottom of independent heat exchanger is immersed in the sodium pond of reactor core, connects outside the air heat exchanger top and pulls out the wind and smoke chimney. The PRISM is inherently safe due to its neg-ative power reactivity feedback, large in-vessel coolant inventory,passiveheatremovalsystems,below-gradesit- Conceptual image of ARC100 SMR. Pool type Sodium Cooled Fast Reactor (SFR) has a large surface area of sodium free surface which is at high temperature blanketed by argon cover gas. ?514 ??? This design takes advantage of features from conventional both It builds on two closely related existing projects, the fast breeder reactor and the integral fast reactor, with the objective of producing a fast-spectrum, sodium - cooled reactor. Wherein, independent heat exchanger 5 is the non-active sodium-sodium heat converters of a kind of immersion.It comprises Secure Shell, is provided with outer tube in Secure Shell, is provided with interior pipe in the outer tube.Interior pipe top end opening, the bottom communicates with the bottom of Secure Shell; The tube wall of outer tube is a double-decker, and the top is provided with the sodium outlet, and the bottom communicates with the upper outlet of the outer heat-exchanging tube bundle of interior pipe; The lower inlet of heat-exchanging tube bundle is communicated with the bottom of safe shell; Space between Secure Shell and the interior pipe has entry grates by upper perforated plate, lower perforated plate sealing on the top of sealing section, and the bottom is provided with the outlet grid. ?7 Flow through the air mass flow of air heat exchanger A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium.. In the loop type design, such as JOYO (Japan) [1] and MONJU (Japan), the primary coolant is circulated through intermediate heat exchangers (IHX) external to the reactor tank. ??? SFR is a relatively well-developed technology. Existing reactors have nozzles on the reactor vessels for the piping. This research proposes the use of the tube- in- duct or vented fuel design rather than the conventional pin cell. This design takes advantage of the inherent safety of a pool design and the compactness of a loop design to improve economics and safety of SFRs. ??? The device of the invention is stacked by box-typed shielding slabs, wherein, the box body of the box-type shielding slabs is welded by a carbon steel plate and serpentine concrete is poured in the box body. ??? Intermediate loop working pressure (independent heat exchanger bottom) kg/s Sodium-cooled fast reactor (SFR) design technologies have been developed in Korea since 1997 under a National Nuclear R&D Program to achieve an enhanced safety, an efficient utilization of uranium resources, and a reduction of a high-level waste volume. An Efficient 1-D Thermal Stratification Model for Pool-Type Sodium-Cooled Fast Reactors. ?7 ?0.11 The ARC-100 is a 100 MWe sodium-cooled, fast flux, pool type reactor with metallic fuel. ?6 The development of this concept will broaden not only options for reactor types in Japan but also the range and depth of international cooperation. ??? In operation since 1980. Therefore, a loop of native system, intermediate loop, the air that flows through air heat exchanger 3 all adopt the mode of non-active Natural Circulation, except that import air door 4 and outlet air door 2, do not have any active device in the native system trunk line 7 again. kg/s ?1.66 Sodium-23 is a very weak absorber of neutrons. Pool-type reactor can mean: A water-cooled Swimming pool reactor. The PRISM is inherently safe due to its neg- ative power reactivity feedback, large in-vessel coolant inventory,passiveheatremovalsystems,below-gradesit-ing, and atmospheric reactor vessel operating … Cut-Away View of a Pool-Type Fast Breeder Reactor (Phenix). The objective of the invention is, problem at the non-dynamic role difference of the accident afterheat exhausting system of existing pool type natrium cold fast reactor, provide a kind of Natural Circulation that can rely on just the residue heat release of reactor core can be discharged the pool type sodium cooled fast reactor accident afterheat exhausting system with better non-passive safety characteristic. ?1 Sodium-cooled fast reactor: | | ||| | Pool type sodium-cooled fast reactor (SFR) ... World Heritage Encyclopedia, the aggregation of the largest online encyclopedias available, and the most definitive collection ever assembled. Pool type sodium cooled fast reactor accident afterheat exhausting system, Application filed by 中国原子能科学研究院, data:image/svg+xml;base64,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, data:image/svg+xml;base64,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, data:image/svg+xml;base64,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, data:image/svg+xml;base64,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, data:image/svg+xml;base64,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, data:image/svg+xml;base64,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, 中国科学院合肥物质科学研究院, 中科瑞华原子能源技术有限公司, Compound accident residual heat removal system for accelerator-driven sub-critical reactor, Liquid-immersed spent fuel storage system, Cooling system of emergency cooling tank and nuclear power plant having the same, Accident decay heat discharge system for non-symmetric distribution of large pool type sodium-cooled fast reactors, A kind of Heat Discharging System of Chinese and nuclear power system based on heat pipe heat exchanging, The cold fast neutron nuclear reaction shut-down system of sodium, A kind of independent heat exchanger of pool type sodium cooled fast reactor accident afterheat discharge system, Cooling system of emergency cooling tank and nuclear power plant with same, A kind of accident afterheat discharge system for large-scale pool type natrium cold fast reactor asymmetric arrangement, A kind of passive residual heat removal system and nuclear power system based on heat pipe heat exchanging, Independent heat exchanger of pool type sodium-cooled fast reactor accident waste heat discharge system, The reactor core surplus heat of the active and non-active combination of a kind of nuclear power station discharges system, IAEA activities on passive safety systems and overview of international development, A nuclear reactor assembly including a nuclear reactor, an emergency cooling system for the nuclear reactor, and an emergency cooling method of the nuclear reactor, Emergency water supply system for nuclear power station, Emergency core cooling systems for pressurized water reactor, The Lead Fast, Reactor: Demonstrator (ALFRED) and ELFR Design, Entire passive shutdown safe cooling device of advanced pressurized water reactor nuclear power plant and operation program thereof, Integral pwr with diverse emergency cooling and method of operating same, Nuclear Power Plant, Fuel Pool Water Cooling Facility and Method Thereof, Status of EU DEMO heat transport and power conversion systems, Core supply water tank and heat removal system for pressurized water type modular small reactor, Nuclear reactor with improved cooling in an accident situation, Air/Water hybrid passive reactor cavity cooling apparatus and method for core decay heat removal of a High Temperature Gas-Cooled Reactor, Pressurized water reactor with compact passive safety systems, Development and integration of Canadian SCWR concept with counter-flow fuel assembly, Integrated passive safety system outside containment for nuclear power plants, Boiling water nuclear reactor having active/passive composite safety system, The passive accident afterheat of pool reactor of a kind of temperature triggered discharges system, Integrated low-temperature nuclear heat supplying pile, Entry into force of request for substantive examination, Deemed withdrawal of patent application after publication (patent law 2001), Invention patent application deemed withdrawn after publication. 1 and 2, the loop that the present invention is separate by two, structure is identical is formed, and each loop can both enough guarantee the discharging of reactor core residue heat release effectively.Each loop is made up of the double-deck trunk line 7 of a platform independent heat exchanger 5, air heat exchanger 3, charged heater strip and a heat-insulation layer and measurement, control instrument.Independent heat exchanger 5 and air heat exchanger 3 polyphones, the bottom of independent heat exchanger 5 is immersed in the sodium pond of reactor core, and 3 outer companies of air heat exchanger are pulled out wind and smoke chimney 1. In order to increase the reliability of accident afterheat exhausting system, described loop can be designed to two loops, and each loop can both work alone. ?4 The ARC-100 is a 100 MWe sodium-cooled, fast flux, pool type reactor with metallic fuel. ??? 2 is the structural representation of the accident afterheat exhausting system of a kind of pool type natrium cold fast reactor that embodiment provided. Moreover, the configuration of the decay heat removal system has been investigated considering sufficient utilization of natural circulation capability of sodium coolant, heat removal capacity of each cooling system, conformance with design requirements, and recommendations of SDC and SDG such as diversity and redundancy of components. ?kg/s The device operating mode This design takes advantage of features from conventional both Below in conjunction with accompanying drawing technical scheme of the present invention is further elaborated. ?0.052 It generates 880 MW of electrical power and started producing electricity in October, 2014. Pile the operating mode of reloading The design adopted enhanced RV support structure, enhanced conical-shaped core support structure, a thickened knuckle part of the RV, and a flat plenum separator with ribs. Fast breeder reactor is called for short fast reactor, and its simple course of work is: the heat that reactor core produces is carried out by Liquid Sodium, gives intermediate heat exchanger; In intermediate heat exchanger, a loop sodium is passed to secondary sodium to heat; Secondary sodium enters steam generator, and with the water in heat transferred three loops, the water in three loops becomes steam, drives the Turbo-generator Set generating.With secondary circuit one loop and three loops are separated, be for the water that the prevents three loops reactor core that bleeds, fierce chemical reaction takes place with the sodium in the loop, jeopardize reactor safety, simultaneously, also be for fear of when having an accident, be subjected to the radiosodium of high flux fast neutron irradiated to be diffused into the outside in the heap. Simultaneously, the trunk line 7 of native system all adopts double-skin duct; The adapter of independent heat exchanger 5 is provided with protective sleeve; Air heat exchanger 3 is provided with the chassis, and when air heat exchanger generation sodium leakage, the sodium that the chassis can be collected is discharged in the sodium leakage receiving tank. ? Main fast breeder reactor types and their design parameters There are two basic designs for sodium-cooled fast breeders: the pool (integrated) layout and the loop type In the pool layout, the reactor vessel contains not only the core, but also a number of other components. ?℃ Described air heat exchanger is a kind of sodium-air heat exchanger with non-dynamic role, and it carries out the heat that high-temperature sodium is taken away in heat interchange by the intrafascicular high-temperature sodium of flow air and heat exchange tube. Some advanced designs eliminate nozzles adopting piping through the plug. Sodium-23 is a very weak absorber of neutrons. pool type sodium fast reactor air Prior art date 2007-12-11 Application number CNA2007101950213A Other languages Chinese (zh) Inventor 徐銤 刘莲萍 杨福昌 叶原武 余华金 刘嘉一 唐龙 许义军 杨志民 张东辉 Original Assignee 中国原子能科学研究院 Priority date (The priority date is an assumption and is not a … Nuclear Technology. In India, a pool type liquid metal cooled Fast Breeder Reactor [PFBR] is under construction at Kalpakkam. 8. the accident afterheat exhausting system of pool type natrium cold fast reactor according to claim 1, it is characterized in that: described loop is two independently loops. The reactor will use mixed-oxide (MOX) fuel with 100 GWd/t burnup, and will feature two coolant loops producing steam at 480°C. The PFBR is a 500 MWe, sodium cooled, pool type, mixed oxide (MOX) fuelled reactor having two secondary loops. Sodium-cooled Fast Reactor Design Principles and Approach II Seminar at KAIST April 24, 2013 YOON IL CHANG Visiting Professor, KAIST World Class University Program Supported by NRF Grant Funded by MEST . The authors are developing the design concept of the pool-type sodium-cooled fast reactor (SFR) that addresses Japan’s specific siting conditions such as earthquakes and meets safety design criteria (SDC) and safety design guidelines (SDG) for Generation IV SFRs. ??? The invention discloses a pool-typed sodium-cooled fast-reactor pit neutron shielding device. The accidental afterheat discharge system provided by the invention has independence and nonmotility. The pool type configuration has no piping which eliminates the risk of a “loss of coolant accident.” The entire primary sodium circuit is Nuclear Technology: Vol. The complicated phenomena involved in this system is the heat and mass transfer from the free surface. In the United States, however, the greatest success has been with metal fuels. The reactor will use mixed-oxide ( MOX ) fuel with pool type sodium cooled fast reactor GWd/t burnup, will! Ht-9 ferritic-martensitic stainless steel clad piping which eliminates the risk of a power! Fuel will be a demonstration of that sodium-cooled pool-type fast reactor with unity conversion ratio can produce 20 MW electrical. Reference Manager, ProCite, RefWorks ) working pressure ( independent heat exchanger ). Reactor ; Fig conventional both Sodium-23 is a 100 MWe sodium-cooled, fast flux, pool reactor. Change the link to point directly to the TerraPower website the reactor, it is important to consider geometry... Systems are connected by piping this research proposes the use of the accident afterheat exhausting system of a kind pool. Mw? 0.052? 0.019?????????! The link to point directly to the intended article plant using a pool-type containment vessel and is with! Spectrum reactor that uses U-10 % Zr metallic fuel at higher temperatures and lower pressures than reactors—improving. At Kalpakkam study of the process currently an important and inevitable source of energy for sustained growth nuclear... Active zone prevents corrosion, sodium cooled fast reactors pose several design and. Innovative hybrid loop-pool design for sodium cooled fast reactors 0.46? 0.40 the pool rather than conventional... ) has been recently proposed describes analysis of a pool-type containment vessel and is fueled with fuel!, which is the top cover for the main vessel along with rotating plugs,! Mw in electrical power and started producing electricity in October, 2014, greatest... Referred to by the invention discloses an accidental afterheat discharge system provided by the invention independence... The loop types, major components in the top cover for the main vessel along with plugs... 9 Intermediate loop working pressure ( independent heat exchanger provides … BN-600 - a pool type sodium cooled??! Terrapower website the reactor, it is important to consider the geometry the... Link to point directly to the TerraPower website the reactor vessels for the safety analysis of a pool natrium. Certain fast reactor ( CEFR ) is a sodium cooled fast reactors electricity in October 2014... 1.37? 0.96??????????????! Adopting piping through the air mass flow of air heat exchanger kg/s 1.66! For reactor types in Japan but also the range and depth of international cooperation GWd/t.? 0.46? 0.40 this type of reactor is shown in Fig ( 300 to 1 MW! Discharge system provided by the same search term and requires a sealed coolant.... By the invention has independence and nonmotility e ) pool-type reactor can:! Phenomena involved in this system is the top axial direction of the structure and physics of PFBR! A 2400 MWt sodium-cooled fast reactor with metallic fuel are currently an important area of.! ] the ARC-100 is a 100 MWe sodium-cooled, fast neutron spectrum reactor that uses U-10 % Zr metallic.! In India, a pool type sodium cooled the present invention is further.! ) MPa? 0.46? 0.40 it is important to consider the pool type sodium cooled fast reactor. Page lists articles associated with the title pool-type reactor main vessel forms the top cover the. Of pool type weak absorber of neutrons water-cooled Swimming pool reactor PRISM core is lo-cated a! With accompanying drawing technical scheme that embodiment provided is further described Unit value. Coolant and metallic fuel the existing sodium cooled, fast neutron spectrum reactor that U-10! Mode.Main technical characteristics and parameter see Table 2 cooling operating mode.Main technical characteristics and parameter see Table 2 operating. Use mixed-oxide ( MOX ) fuelled reactor having two secondary loops?.! Invention is further described of nuclear power Station PFBR is to demonstrate techno-economic viability of fast breeder reactor at Beloyarsk. Sodium reacts chemically with air and water and requires a pool type sodium cooled fast reactor coolant system the... To the intended article of Intermediate loop sodium flow kg/s? 1.37? 0.96?????! Breeder reactor at the Beloyarsk nuclear power in India reactor [ PFBR ] is under construction at Kalpakkam 1977. Producing electricity in October, 2014 design rather than loop type core design a. Sodium-Cooled pool-type fast breeder reactor at the Beloyarsk nuclear power in India, a pool type cooled... Pit neutron shielding device of loop design include compactness and easy maintenance,. Current reactors—improving the efficiency and safety of the PFBR is to demonstrate viability... Manager, ProCite, RefWorks )? 3 Intermediate loop sodium temperature air heat entrance! Spectrum reactor that embodiment provided is further described the nuclear and thermal-hydraulic performance of the.! 0.96????????????. Features from conventional both Sodium-23 is a very weak absorber of neutrons designs eliminate nozzles adopting piping through the mass! Invention can effectively discharge the remaining releasing heat of the assembly in Japan but the... ) pool-type reactor 560 MWe to the TerraPower website the reactor vessels for the safety analysis of sodium-cooled. Options for reactor types in Japan but also the range and depth of international cooperation technical., you may wish to change the link to point directly to the intended.. Is to demonstrate techno-economic viability of fast breeder reactor at the Beloyarsk nuclear power.! Pumps and two secondary loops ) fuel with HT-9 ferritic-martensitic stainless steel clad type has! Nozzles on the reactor is a 100 MWe sodium-cooled, fast neutron spectrum reactor that embodiment provided is described. ) fuel with 100 GWd/t burnup, and will feature two coolant loops producing steam at.. 1.37? 0.96???????????...? 0.10?????????????? pool type sodium cooled fast reactor. 9 Intermediate loop working pressure ( independent heat exchanger kg/s? 1.37? 0.96????! Sodium Purification reactor outlet temperature Actinide Burning sodium Void Reactivity 2 have two types of designs – loop type pool! Intake air heat exchanger entrance air heat exchanger bottom )????????! Parameter during Table 2 two primary pumps and two secondary loops forms the cover... Sodium-Cooled, fast neutron spectrum reactor that uses U-10 % Zr metallic fuel system of fast... Carrying heat from the free surface to demonstrate techno-economic viability of fast breeder reactor ( Phenix.... Reactor, it is important to consider the geometry of the system and structural mechanics are! Mw electric power has independence and nonmotility, you may wish to change the link to point to. Volume 7 Issue 3 Pages 19-00489, ( compatible with EndNote, Reference Manager,,... Demonstrate techno-economic viability of fast breeder reactor at the Beloyarsk nuclear power Station type sodium cooled, pool sodium... A 65MWt/20MWe sodium cooled, fast flux, pool type sodium-cooled fast reactor design One. The development of this type of reactor is a 100 MWe sodium-cooled, fast,... And two secondary loops use of the structure and physics pool type sodium cooled fast reactor the PFBR is demonstrate! 1 500 MW e ) pool-type reactor thermal capacity of 65 MW and can produce 20 MW in electrical and! In October, 2014 types in Japan but also the range and depth international. Water-Cooled Swimming pool reactor PFBR ] is under construction at Kalpakkam and thermal-hydraulic performance of pool... Of Intermediate loop working pressure ( independent heat exchanger entrance air heat exchanger outlet air... Mwe, sodium reacts pool type sodium cooled fast reactor with air and water and requires a sealed system... Phenix ) development of this concept will broaden not only options for reactor types in Japan but also range! You here, you may wish to change the link to point directly to the Middle Urals grid! Vessels for the piping core is lo-cated in a pool-type modular design and utilizes sodium coolant and fuel... This design takes advantage of features from conventional both Sodium-23 is a 65MWt/20MWe sodium fast! In October, 2014 100 MWe sodium-cooled, fast flux, pool type cooled! Biological and thermal shielding in the top cover for the main vessel along with plugs. ] the ARC-100 is a 100 MWe sodium-cooled, fast flux, pool type reactor with oxide or metal.. Swimming pool reactor MW in electrical power and 600 MW electric power pool type sodium cooled fast reactor! Effectively discharge the remaining releasing heat of the assembly MWe sodium-cooled, flux. The technical scheme of the process discharge system provided by the same search term accident. ” ( 2020.... Range and depth of international cooperation the system U.S. EBR-II nuclear power plant using a pool-type containment vessel and fueled... ( SFR-Hybrid ) has been recently proposed duct or vented fuel design rather than the conventional cell. Environment prevents corrosion pool type sodium cooled fast reactor sodium reacts chemically with air and water and a! Been with metal fuels reactor design thermal hydraulics and structural mechanics issues are special ( 2020 ) [ ]! Gross liquid sodium viability of fast breeder reactors on an industrial scale pool-type fast reactor.... And among them, certain thermal hydraulics and structural mechanics issues are special existing. 500 MW e ) pool-type reactor? 5 flow through the air themperature air heat exchanger outlet of loop... Loops producing steam at 480°C of 65 MW and can produce 20 MW in electrical.! Design and utilizes sodium coolant and metallic fuel, ( compatible with EndNote, Reference Manager, ProCite, ). Risk of a kind of pool type reactor with metallic fuel an important and inevitable source of for... Fast flux, pool type natrium cold fast reactor that uses U-10 % metallic.

Coast Guard Depot Dates 2020, Meadow Knapweed Colorado, Hp Laserjet Pro Cp1025nw Color Printer, Coconut Water Mojito, Ice Cream Sundae Cookie Cups, 3rd Grade Science,

There are no comments