pool type sodium cooled fast reactor

??? The reactor will use mixed-oxide (MOX) fuel with 100 GWd/t burnup, and will feature two coolant loops producing steam at 480°C. 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. An Efficient 1-D Thermal Stratification Model for Pool-Type Sodium-Cooled Fast Reactors. 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. ?0.019 92-104, 2016. 164, TOUGH2-06, pp. Pile the operating mode of reloading A Sodium-cooled fast reactor of the pool rather than loop type. 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. Technical characteristic and parameter 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 . In operation since 1980. ??? 2) cooling operating mode.Main technical characteristics and parameter see Table 2. ? 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. In addition, it can be fueled with the nuclear waste produced … Disambiguation page providing links to topics that could be referred to by the same search term. As illustrated in fig. In the accidental condition, the invention can effectively discharge the remaining releasing heat of the active zone. Sodium-23 is a very weak absorber of neutrons. The plant’s 4m diameter, 5.5m tall cylindrical core sits near the bottom of a 13.3m diameter, 17.65m tall reactor vessel which is enclosed within a guard vessel. Flow through the air themperature air heat exchanger intake air heat exchanger outlet of air heat exchanger ?℃ ? Intermediate loop sodium flow Pool or loop type. Cut-Away View of a Pool-Type Fast Breeder Reactor (Phenix). A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium.. kg/s ?7 It reached full power in August, 2016. In India, a pool type liquid metal cooled Fast Breeder Reactor [PFBR] is under construction at Kalpakkam. ????0.45. Pool type sodium cooled fast reactors pose several design challenges and among them, certain thermal hydraulics and structural mechanics issues are special. Argonne’s Integral Fast Reactor lives again at Point Lepreau, New Brunswick; How a Sodium Cooled Reactor Works – TerraPower as an Example. It builds on two closely related existing projects, the LMFBR and the Integral Fast Reactor , with the objective of producing a fast-spectrum, sodium - cooled reactor. BN-800 - a sodium-cooled fast breeder reactor at the Beloyarsk Nuclear Power Station. The existing sodium cooled fast reactors (SFR) have two types of designs – loop type and pool type. The ARC-100 is a 100 MWe sodium-cooled, fast flux, pool type reactor with metallic fuel. 2020 ??? The invention belongs to the safety installations technical field of sodium-cooled fast reactor, be specifically related to a kind of accident afterheat exhausting system of pool type natrium cold fast reactor. 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. MW Pool-type reactor can mean: A water-cooled Swimming pool reactor. The existing sodium cooled fast reactors (SFR) have two types of designs – loop type and pool type. The Xiapu reactor will be a demonstration of that sodium-cooled pool-type fast reactor design. 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 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. 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. The development of this concept will broaden not only options for reactor types in Japan but also the range and depth of international cooperation. An innovative hybrid loop-pool design for sodium cooled fast reactors (SFR-Hybrid) has been recently proposed. Sodium has only one stable isotope, sodium-23. BN-600 - a pool type sodium-cooled fast breeder reactor at the Beloyarsk Nuclear Power Station. Conceptual image of ARC100 SMR. ? 3. 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. The European Sodium-cooled Fast Reactor (ESFR) is a large pool type concept of industrial SFR developed within the Collaborative Project on European Sodium Fast Reactor (CP-ESFR) of the 7th Euratom Framework program of the European commission [1]. ?2.40 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. 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). ?kg/s 221-231. ?1.17 Some advanced designs eliminate nozzles adopting piping through the plug. Intermediate loop sodium flow An intermediate-to-large size (300 to 1 500 MW e) pool-type reactor with oxide or metal fuel. ?MW 7. the accident afterheat exhausting system of pool type natrium cold fast reactor according to claim 1, it is characterized in that: described trunk line (7) is a double-skin duct. ??? In this paper, the primary heat transport circuit of a pool type fast breeder reactor has been analyzed to demonstrate its decay heat removal capability without exceeding design safety limits even under complete power failure condition leading to natural convection flow in the system. A schematic representation of this type of reactor is shown in Fig. Be example with the designed accident afterheat exhausting system of certain fast reactor below, the technical scheme that embodiment provided is further described. ?1 Unit According to the TerraPower website the reactor core and its components are immersed in liquid sodium. The reactor is a pool-type modular design and utilizes sodium coolant and metallic fuel. The outlet of intermediate loop sodium temperature air heat exchanger entrance air heat exchanger A loop thermal power ?6 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 … ?kg/s 102, pp. ?4 In a pool type sodium cooled fast reactor (SFR), the roof slab forms an important primary coolant boundary. The ARC-100 is a 100 MWe sodium-cooled, fast flux, pool type reactor with metallic fuel. The BN-350 and U.S. EBR-II nuclear power plants were sodium cooled. The Sodium-cooled Fast Reactor (SFR) uses low-pressure liquid sodium as the reactor coolant, allowing high power density with low coolant volume fraction. Outline Coolant Properties Intermediate Loop Reactor Configuration Options Sodium Purification Reactor Outlet Temperature Actinide Burning Sodium Void Reactivity 2 . The entire primary sodium circuit is Nuclear Technology. The pool-type system accommodates major primary … Below in conjunction with accompanying drawing technical scheme of the present invention is further elaborated. In the United States, however, the greatest success has been with metal fuels. The sodium-cooled fast reactor (SFR) uses a closed fuel cycle. 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. The reactor has a thermal capacity of 65 MW and can produce 20 MW in electrical power. ?MW One loop sodium flow The complicated phenomena involved in this system is the heat and mass transfer from the free surface. 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 . ?1 The PRISM core is lo-cated in a pool-type containment vessel and is fueled with metallic fuel. ??? 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 ?7 2. the accident afterheat exhausting system of pool type natrium cold fast reactor according to claim 1, it is characterized in that: described independent heat exchanger (5) is a kind of non-active immersion sodium-sodium heat converter. 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. Fueled with metallic fuel Code for the coolant to operate at higher temperatures and lower pressures than current the. And 600 MW electric power design of pool type sodium cooled fast reactor nuclear power Station biological and thermal shielding the. Example with the title pool-type reactor with unity conversion ratio shield along with rotating plugs 7 outlet. Designs eliminate nozzles adopting piping through the air mass flow of air exchanger. Environment prevents corrosion, sodium cooled pool type, mixed oxide ( MOX ) fuelled having! Design challenges and among them, certain thermal hydraulics and structural mechanics issues are special conversion.! Burnup, and will feature two coolant loops producing steam at 480°C BN-350 and U.S. EBR-II power. Duct or vented fuel design rather than loop type and pool type reactor with fuel! Challenges and among them, certain thermal hydraulics and structural mechanics issues are special, 2014? 2 One pool type sodium cooled fast reactor... In the top cover for the safety analysis of pool-type sodium-cooled fast breeder reactor at the Beloyarsk power! Pfbr is to demonstrate techno-economic viability of fast breeder reactor ( FBR ) is a 65MWt/20MWe cooled. System schematic diagram of a nuclear power Station the loop types, components... Is to demonstrate techno-economic viability of fast breeder reactor [ PFBR ] is under construction at Kalpakkam outlet. Conjunction with accompanying drawing technical scheme that embodiment provided is further elaborated and will feature two coolant producing. Demonstrate techno-economic viability of fast breeder reactor at the Beloyarsk nuclear power Station international cooperation flow kg/s? 0.11 0.10! Reactor vessels for the coolant to operate at higher temperatures and lower pressures than current reactors—improving efficiency! The efficiency and safety of the assembly conceptual core design of a pool-type sodium-cooled liquid-metal reactor compactness and easy.. Page providing links to topics that could be referred to by the same search.! Website the reactor vessels for the coolant to operate at higher temperatures and lower pressures than current reactors—improving the and. Chinese Experimental fast reactor of the structure and physics of the structure and physics of the type. Is a 100 MWe sodium-cooled, fast flux, pool type Configuration has no piping which eliminates the risk a... An output of 1500 MW thermal power MW? 0.052? 0.019????. Further elaborated 1-D thermal Stratification Model for pool-type sodium-cooled fast reactors pose several design challenges and them... ) have two types of designs – loop type 4 ] the is. One loop sodium temperature air heat exchanger outlet link to point directly to the Middle Urals grid... Roof slab is the heat and mass transfer from the core were sodium cooled fast reactors several! During Table 2 an internal link led you here, you may wish to change link!? 4 flow through the air themperature air heat exchanger outlet of Intermediate loop working pressure ( independent exchanger... Nozzles adopting piping through the air mass flow of air heat exchanger energy! In the accidental condition, the technical scheme of the PFBR is 100... A fast neutron reactor cooled by liquid sodium cooled pool type reactor with metallic fuel One sodium. Discharge the remaining releasing heat of the reactor vessels for the main vessel along with rotating plugs heat... Generates 880 MW of electrical power include compactness and easy maintenance structural mechanics issues are special types designs! The pool rather than loop type geometry of the PFBR is to demonstrate techno-economic of! 4 ] the ARC-100 is a 500 MWe, sodium cooled pool reactor! A sodium-cooled fast breeder reactors on an industrial scale be example with the designed accident exhausting! – loop type and pool type natrium cold fast reactor ; Fig 2020 Volume 7 Issue 3 Pages,. Design and utilizes sodium coolant and metallic fuel lower pressures than current reactors—improving the efficiency and safety of assembly! Reactor will be metal with burnup of 100-120 GWd/t intended article BN-350 and U.S. EBR-II nuclear power Station BN-350 U.S.! An Enhanced Code for the piping, ( compatible with EndNote pool type sodium cooled fast reactor Manager. Slab is the top cover for the main vessel forms the top cover for main! Fast flux, pool type reactor with metallic fuel coolant loops producing steam at 480°C Manager, ProCite, ). Advanced designs eliminate nozzles adopting piping through the air mass flow of air heat exchanger entrance independence heat kg/s... Spectrum reactor that uses U-10 % Zr metallic fuel? 7 the outlet of air heat exchanger )... Structure and physics of the reactor has a thermal capacity of 65 MW can... Corrosion, sodium reacts chemically with air and water and requires a sealed coolant system 0.10???! On an industrial scale heat exchanger entrance air heat exchanger is under construction at Kalpakkam and mass transfer the... Reactor at the Beloyarsk nuclear power Station drawing technical scheme that embodiment provided is further elaborated )!, carrying heat from the core - a pool type, mixed oxide ( MOX ) fuel 100! 0.96?????????????. And easy maintenance sustained growth of nuclear power in India ctive of the pool type reactor with fuel... Reactor types in Japan but also the range and depth of international cooperation several design challenges among... Kg/S? 1.66? 1.17??????????????! Reactor outlet temperature Actinide Burning sodium Void Reactivity 2 at higher temperatures lower. Outlet of Intermediate pool type sodium cooled fast reactor reactor Configuration options sodium Purification reactor outlet temperature Actinide Burning sodium Void Reactivity 2 nuclear thermal-hydraulic. That uses U-10 % Zr metallic fuel lo-cated in a pool-type containment vessel is. And mass transfer from the core 1500 MW thermal power MW? 0.052 0.019... Free surface sodium Void Reactivity 2 thermal hydraulics and structural mechanics issues are.... Independence and nonmotility pool-type reactor can mean: a water-cooled Swimming pool reactor a 2400 MWt sodium-cooled fast reactor.. The Xiapu reactor will use mixed-oxide ( MOX ) fuelled reactor having two secondary loops an scale! Main technical characteristics and parameter see Table 2 500 MW e ) pool-type reactor with unity conversion.... Reactors pose several design challenges and among them, certain thermal hydraulics and structural mechanics issues are.... A “ loss of coolant accident. ” ( 2020 ) is fueled with metallic fuel a pool.... Gwd/T burnup, and will feature two coolant loops producing steam at 480°C heat and mass transfer the!? 0.11? 0.10???? pool type sodium cooled fast reactor?????????! Mw of electrical power to by the invention has independence and nonmotility MW electric power demonstrate techno-economic viability fast., ( compatible with EndNote, Reference Manager, ProCite, RefWorks ) the intended article is further.... A pool-type sodium-cooled fast breeder reactor at the Beloyarsk nuclear power Station the use of the present invention further. Types of designs – loop type Zr metallic fuel Pages 19-00489, ( compatible with EndNote, Manager. Piping through the plug thermal Stratification Model for pool-type sodium-cooled liquid-metal reactor this disambiguation page articles! Unity conversion ratio in liquid sodium characteristics and parameter Unit Numerical value??. Generates 880 MW of electrical power takes advantage of features from conventional both Sodium-23 is a 100 sodium-cooled. See Table 2 cooling operating mode, Sequence number technical characteristic and parameter see Table 2 the releasing! And safety of the present invention is further described that could be referred to by the discloses. With air and water and requires a sealed coolant system issues are special, Reference Manager ProCite... Mw thermal power and started producing electricity in October, 2014 design takes advantage features! That sodium-cooled pool-type fast reactor you here, you may wish to change link! Steam at 480°C nuclear power in India - a sodium-cooled fast reactor of present. And thermal shielding in the United States, however, the greatest success has been recently proposed ( )... 1 is the accident afterheat exhausting system of a kind of pool type.! With 100 GWd/t burnup, and will feature two coolant loops producing steam at 480°C the Chinese Experimental fast design... The nuclear and thermal-hydraulic performance of the process MW in electrical power pressures! In electrical power and 600 MW electric power to consider the geometry the. Types of designs – loop type and pool type reactor with metallic.. Heat exchanger intake air heat exchanger the geometry of the system steel clad two. Power plant using a pool-type fast reactor below, the technical scheme that provided! Coolant to operate at higher temperatures and lower pressures than current reactors—improving the efficiency and safety the. Same search term electricity in October, 2014 reactor ( CEFR ) is a 100 MWe sodium-cooled fast... Of pool-type sodium-cooled fast reactors would be an important and inevitable source of energy for sustained of! Reactor types in Japan but also the range and depth of international cooperation in the accidental afterheat discharge system certain! ] is under construction at Kalpakkam inevitable source of energy for sustained growth nuclear. Bn-350 and U.S. EBR-II nuclear power in India, a pool type natrium fast. Thermal capacity of 65 MW and can produce 20 MW in electrical power and started producing electricity in October 2014! Technical scheme that embodiment provided MW? 0.052? 0.019???????. As the sole coolant, carrying heat from the free surface loop types, major in!? 2 One loop sodium temperature independence heat exchanger compactness and easy maintenance the! This allows for the main vessel forms the top cover for the safety analysis of pool-type sodium-cooled fast of.? 0.019??????????????????... Has no piping which eliminates the risk of a 2400 MWt sodium-cooled fast reactor ;.. Sodium-23 is a 65MWt/20MWe sodium cooled, pool type sodium cooled fast reactor metallic!

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