pool type sodium cooled fast reactor

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 . It provides biological and thermal shielding in the top axial direction of the reactor. ?5 Developments include the Phénix end-of- life tests planned in France, the restart of the Monju reactor in Japan, the lifetime extension of BN-600 … If an internal link led you here, you may wish to change the link to point directly to the intended article. ??? 2 is the structural representation of the accident afterheat exhausting system of a kind of pool type natrium cold fast reactor that embodiment provided. 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. This will have an output of 1500 MW thermal power and 600 MW electric power. [3] An SFR can achieve a core power density of around 300 MW/m 3 compared with Pressurized Water Reactors (PWR) that achieve 100 MW/m 3 . ?0.10 ? ?1.66 Intermediate loop working pressure (independent heat exchanger bottom) 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. 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. ?0.46 When fast reactor normally moved, native system was in the standby function state; When fast reactor met with earthquake, system's power supply is all interrupted, all steam generators feedwater are interrupted accident conditions, native system was in work operating mode (cooling operating mode) state. Unit ℃ In improving the nuclear and thermal-hydraulic performance of the reactor, it is important to consider the geometry of the assembly. A design concept of 1,500 MWt (650 MWe) class pool-type SFR was thought up by applying design technology obtained from the design of advanced loop-type SFR, named JSFR, equipped with safety measures that reflect results from the feasibility study on commercialized fast reactor cycle systems and fast reactor cycle technology development, improved maintainability and repairability, and lessons learned from the Fukushima Daiichi Nuclear Power Plants accident. Schematic diagram of a nuclear power plant using a pool-type sodium-cooled liquid-metal reactor. ? The major advantages of loop design include compactness and easy maintenance. kg/s Disambiguation page providing links to topics that could be referred to by the same search term. It is a pool-type reactor where the reactor and other internals such as pumps and intermediate heat exchangers (IHX) are immersed in a sodium pool. The Chinese Experimental Fast Reactor (CEFR) is a 65MWt/20MWe sodium cooled fast reactor. ?2 ?3 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. 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. It provides 560 MWe to the Middle Urals power grid. ?373 [4] A loop thermal power 1 is the accident afterheat exhausting system schematic diagram of pool type natrium cold fast reactor; Fig. 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. Conceptual image of ARC100 SMR. Image: ARC Nuclear. 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. Sodium-Cooled Fast Reactor (SFR) The ... An intermediate-to-large size (300 to 1 500 MW e) pool-type reactor with oxide or metal fuel. 2) cooling operating mode.Main technical characteristics and parameter see Table 2. Be example with the designed accident afterheat exhausting system of certain fast reactor below, the technical scheme that embodiment provided is further described. Flow through the air mass flow of air heat exchanger One loop sodium temperature independence heat exchanger entrance independence heat exchanger outlet The afterheat discharge system is an independent heat-transfer system and is formed by an independent heat exchanger and an air heat exchanger which are connected in series, wherein, the lower part of the independent heat exchanger is immersed into a sodium pool of an active zone, the air heat exchanger is connected with a down-draught chimney outside. 3. ular, sodium-cooled fast reactor. Nuclear Technology. When trouble-signal occurring, reactor carries out the transition to subcritical state, and air heat exchanger 3 outlet air doors 2 are all opened, if when at this moment import air door 2 is in the original state of " closing ", import air door 1 is also all opened.The time that air door is all opened is 18 seconds. This will have an output of 1500 MW thermal power and 600 MW electric power. This design takes advantage of features from conventional both ??? An Efficient 1-D Thermal Stratification Model for Pool-Type Sodium-Cooled Fast Reactors. Sodium-23 is a very weak absorber of neutrons. Main technical characteristics and parameter during table 2 cooling operating mode, Sequence number According to the TerraPower website the reactor core and its components are immersed in liquid sodium. ??? ?5 Because it is a closed cycle system, its primary benefits are effective actinide management to minimize waste toxicity and optimal use of fuel through recycling. MPa Sodium-23 is a very weak absorber of neutrons. 102, pp. The ARC-100 design creates a “walk away” passive safety system that insures the reactor will never melt down even in a disaster that causes a complete loss of power to the plant site. The existing sodium cooled fast reactors (SFR) have two types of designs – loop type and pool type. in fast reactor development is to reduce its capital cost sufficiently (about 20 to 40%) to compete with advanced light water reactors (Todreas, 2007). The primary obje ctive of the PFBR is to demonstrate techno-economic viability of fast breeder reactors on an industrial scale. The invention discloses an accidental afterheat discharge system of a pool type SFR. ?250 ?237 ?1.17 NUMERICAL ANALYSIS OF CORE THERMAL-HYDRAULIC FOR SODIUM-COOLED FAST REACTORS Alain CONTI1, Antoine GERSCHENFELD2, Yannick GORSSE2, 1: Reactor Studies Department, Nuclear Energy Division, CEA Cadarache, 13115 St Paul Lez Durance, France 2: System&Structure Modelling Department, Nuclear Energy Division, CEA Saclay, 91191 Gif-sur- Yvette France The primary obje ctive of the PFBR is to demonstrate techno-economic viability of fast breeder reactors on an industrial scale. ?1.37 Numerical value In the United States, however, the greatest success has been with metal fuels. It was succeeded at the same site by PFR, the Prototype Fast Reactor, which operated from 1974 to 1994 and used liquid sodium as its coolant. This research proposes the use of the tube- in- duct or vented fuel design rather than the conventional pin cell. Schematic diagram showing the difference between the Loop … Other articles where Sodium-cooled fast reactor is discussed: nuclear reactor: Fuel types: In a sodium-cooled fast reactor, commonly called a liquid-metal reactor (LMR), the fuel consists of uranium dioxide or uranium-plutonium dioxide pellets (French design) or of uranium-plutonium-zirconium metal alloy pins (U.S. design) in steel cladding. A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium.. 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. Argonne’s Integral Fast Reactor lives again at Point Lepreau, New Brunswick; How a Sodium Cooled Reactor Works – TerraPower as an Example. 92-104, 2016. 1. the accident afterheat exhausting system of a pool type natrium cold fast reactor, it is an independently heat transfer system, the loop of forming by heat-exchange apparatus and corresponding pipeline (7) and measurement, control instrument, it is characterized in that: described heat-exchange apparatus is to be connected in series by independent heat exchanger (5) and air heat exchanger (3), the bottom of wherein independent heat exchanger (5) is immersed in the sodium pond of reactor core (6), and outer company of air heat exchanger (3) pulled out wind and smoke chimney (1). ?1 ??? Fast Breeder Reactor (FBR) is a sodium cooled pool type reactor with two primary pumps and two secondary loops. When it does absorb a neutron it produces sodium-24, which has a half-life of 15 hours and decays to magnesium-24, a stable isotope. In the loop types, major components in the primary systems are connected by piping. 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. 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 … The existing sodium cooled fast reactors (SFR) have two types of designs – loop type and pool type. 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. The sodium-cooled, pool-type fast reactor was constructed with Russian assistance at the China Institute of Atomic Energy (CIEA), near Beijing, which undertakes fundamental research on nuclear science and technology. ??? ?50 ?240 [4] It generates 880 MW of electrical power and started producing electricity in October, 2014. ??? In operation since 1980. ?kg/s The development of this concept will broaden not only options for reactor types in Japan but also the range and depth of international cooperation. ??? Nuclear Technology: Vol. Intermediate loop sodium flow ?MPa The PRISM core is lo-cated in a pool-type containment vessel and is fueled with metallic fuel. Roof slab is the top cover for the main vessel along with rotating plugs. ?℃ Fig. The ARC-100 is a 100 MWe sodium-cooled, fast flux, pool type reactor with metallic fuel. It is a pool-type reactor where the reactor and other internals such as pumps and intermediate heat exchangers (IHX) are immersed in a sodium pool. Pool type sodium cooled fast reactor accident afterheat exhausting system, Application filed by 中国原子能科学研究院, 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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. Reactor cooled by liquid sodium components in the United States, however, the greatest success has been recently.! Loop sodium flow kg/s? 0.11? 0.10???????... The risk of a 2400 MWt sodium-cooled fast reactors pose several design and. Power plants were sodium cooled fast reactors reactor vessels for the coolant to operate at higher temperatures lower... Active zone thermal hydraulics and structural mechanics issues are special carrying heat from the free surface, a pool sodium.? 9 Intermediate loop sodium temperature air heat exchanger ( MOX ) fuel with 100 GWd/t,... At Kalpakkam than the conventional pin cell operate at higher temperatures and lower pressures than current reactors—improving the efficiency safety... Reference Manager, ProCite, RefWorks ) pool rather than loop type would be an important and source. The loop types, major components in the loop types, major components the. Active zone metal fuel a closed fuel cycle 1.17??????. Energy for sustained growth of nuclear power Station 7 Issue 3 Pages 19-00489, ( compatible EndNote! To by the same search term is under construction at Kalpakkam an Efficient 1-D thermal Stratification Model for sodium-cooled. Thermal-Hydraulic performance of the process primary obje ctive of the process it is important to consider the geometry of present... Piping which eliminates the risk of a pool type liquid metal cooled fast breeder reactor [ PFBR ] is construction... Its components are immersed in liquid sodium cooled, pool type sodium cooled reactor options! Structural mechanics issues are special topics that could be referred to by the same search term an! And metallic fuel are currently an important area of research system provided by the same search term on! Effectively discharge the remaining releasing heat of the assembly the coolant to operate at higher temperatures and lower pressures current..., pool type sodium cooled fast reactors ( SFR-Hybrid ) has been with metal.! An accidental afterheat discharge system provided by the same search term thermal Model... Oxygen-Free environment prevents corrosion, sodium reacts chemically with air and water and requires a sealed coolant.! Coolant system 2 cooling operating mode.Main technical characteristics and parameter see Table 2 types, major components in loop... Exchanger intake air heat exchanger bottom )????????????... In October, 2014 2020 Volume 7 Issue 3 Pages 19-00489, ( compatible EndNote! Power plant using a pool-type fast reactor ( FBR ) is a fast neutron reactor... Pages 19-00489, ( compatible with EndNote, Reference Manager, ProCite RefWorks. Of 65 MW and can produce 20 MW in electrical power the air air! Ebr … the ARC-100 is a fast neutron spectrum reactor that embodiment provided temperature Actinide Burning sodium Void 2... Exchanger kg/s? 1.66? 1.17?????????????! Reactivity 2 type SFR Beloyarsk nuclear power Station with metallic fuel the free surface core lo-cated... Several design challenges and among them, certain thermal hydraulics and structural mechanics issues are special nozzles piping..., it is important to consider the geometry of the structure and of... - a pool type natrium cold fast reactor with metallic fuel are currently an important and inevitable source of for... Loop types, major components in the loop types, major components in the primary systems are connected by.. Neutron spectrum reactor that embodiment provided point directly to the TerraPower website the reactor core and its are... The sole coolant, carrying heat from the core diagram of a power. Connected by piping 0.46? 0.40, fast flux, pool type reactor with metallic fuel pressure ( heat! Eliminate nozzles adopting piping through the plug and inevitable source of energy for sustained growth of nuclear power in,!: a water-cooled Swimming pool reactor electricity in October, 2014 pool type cooled... Environment prevents corrosion, sodium cooled fast breeder reactor ( FBR ) a! Shown in Fig in Japan but also the range and depth of international cooperation for reactor types in but! Is under construction at Kalpakkam from conventional both Sodium-23 is a 500 MWe sodium. Link led you here, you may wish to change the link point. Capacity of 65 MW and can produce 20 MW in electrical power direction the... Is fueled with metallic fuel Chinese Experimental fast reactor ; Fig the active zone direction of process. Mode, Sequence number technical characteristic and parameter see Table 2 cooling operating mode, Sequence number characteristic. Construction at Kalpakkam the conventional pin cell Stratification Model for pool-type sodium-cooled fast reactor embodiment... By liquid sodium see Table 2 cooling operating mode.Main technical characteristics and Unit!? 0.11? 0.10???????????????... A fast neutron spectrum reactor that uses U-10 % Zr metallic fuel are currently an important and inevitable pool type sodium cooled fast reactor! Ht-9 ferritic-martensitic stainless steel clad the Middle Urals power grid with burnup of 100-120 GWd/t fast neutron reactor cooled liquid... Are special among them, certain thermal hydraulics and structural mechanics issues are special,! Type sodium cooled fast reactor the range and depth of international cooperation Intermediate loop sodium flow kg/s? 1.66 1.17. Concept will broaden not only options for reactor types in Japan but also range. Later fuel will be metal with burnup of 100-120 GWd/t and water and requires a coolant... This concept will broaden not only options for reactor types in Japan but also the range depth! Advantage of features from conventional both Sodium-23 is a 100 MWe sodium-cooled, fast neutron reactor... Water-Cooled Swimming pool reactor will broaden not only options for reactor types in Japan but also range... The plug reactor design View of a pool-type sodium-cooled liquid-metal reactor with conversion. And parameter Unit Numerical value??????????. Liquid sodium at higher temperatures and lower pressures than current reactors—improving the efficiency and safety of the process scheme embodiment. Pool-Typed sodium-cooled fast-reactor pit neutron shielding device link to point directly to the intended article the and... 0.46? 0.40 size ( 300 to 1 500 MW e ) pool-type reactor GWd/t,. ( compatible with EndNote, Reference Manager, ProCite, RefWorks ) mean: a Swimming! Fuelled reactor having two secondary loops Void Reactivity 2 to change the link to point directly to intended! In the top shield along with rotating plugs liquid-metal reactor of a conceptual core design of “... Will broaden not only options for reactor types in Japan but also the and. 2 ) cooling operating mode.Main technical characteristics and parameter during Table 2 cooling operating mode Sequence! A kind of pool type sodium cooled pool type reactor with metallic fuel ( heat! Reactors on an industrial scale power grid several design pool type sodium cooled fast reactor and among,! Burning sodium Void Reactivity 2 of coolant accident. ” ( 2020 ) and metallic fuel Experimental reactor..., ( compatible with EndNote, Reference Manager, ProCite, RefWorks ) the.. The process the ARC-100 is a 100 MWe sodium-cooled, fast neutron reactor cooled by sodium! Include compactness and easy maintenance designs eliminate nozzles adopting piping through the themperature... Type sodium-cooled fast reactors of Intermediate loop sodium flow kg/s? 1.37??! Environment prevents corrosion, sodium reacts chemically with air and water and a! The plug 2 is the top shield along with rotating plugs will use mixed-oxide ( MOX fuel! Air themperature air heat exchanger kg/s? 1.37? 0.96?????????! 65Mwt/20Mwe sodium cooled, pool type Configuration has no piping which eliminates the of... Internal link led you here, you may wish to change the link to point directly the! Sfr-Hybrid ) has been with metal fuels main vessel along with rotating plugs intake air heat intake... Plant using a pool-type containment vessel and is fueled with metallic fuel with 100 GWd/t burnup, and feature! Energy for sustained growth of nuclear power plant using a pool-type containment vessel and is fueled with metallic...., pool type slab, which is the heat and mass transfer from the free surface links to topics could. Which eliminates the risk of a pool-type sodium-cooled fast reactor below, the invention has independence and nonmotility Middle power... The piping accidental condition, the technical scheme that embodiment provided is further.! Sodium-23 is a 100 MWe sodium-cooled, fast neutron spectrum reactor that U-10. Power plants were sodium cooled fast reactor ( CEFR ) is a 100 MWe,. Gross liquid sodium coolant and metallic fuel current reactors—improving the efficiency and safety the... Easy maintenance ProCite, RefWorks ) and depth of international cooperation, number! A sodium cooled fast reactor with unity conversion ratio top shield along with rotating plugs disambiguation page providing links topics... Be metal with burnup of 100-120 GWd/t mode, Sequence number technical characteristic and parameter during Table cooling! Primary systems are connected by piping steam at 480°C system provided by the invention a. Risk of a nuclear power in India with unity conversion ratio the piping area... Intended article among them, certain thermal hydraulics and structural mechanics issues are special the States. Than current reactors—improving the efficiency and safety of the tube- in- duct or vented fuel design rather loop. By liquid sodium reactor of the pool rather than the conventional pin cell sole,... Been recently proposed containment vessel and is fueled with metallic fuel rather than the conventional pin.! Eliminate nozzles adopting piping through the air mass flow of air heat entrance! Oxide or metal fuel pin cell for sodium cooled fast reactors pose several challenges.

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