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When native system was in standby function, import air door 4 was all opened, and outlet air door 2 is closed, but leaves 10% gap.Close the valve of the argon system of the sodium fill-drain syctem that connects native system and secondary circuit, accident afterheat exhausting system.The sodium of native system intermediate loop enters the expansion drum of air heat exchanger 3 from independent heat exchanger 5 along pipeline under the Natural Circulation effect, and be diverted to the heat exchanger tube tube bank by the latter, and with the heat transferred air, sodium is got back to independent heat exchanger along pipeline.Under the draft effect of pulling out wind and smoke chimney 1, the import air door 4 of air through opening enters in the air heat exchanger 3, and enters atmosphere through exporting air door 2 and pulling out wind and smoke chimney 1.One loop sodium enters the entry grates of independent heat exchanger 5 under the Natural Circulation effect, by shell side, flow to the bottom in reactor " heat " chamber. It provides … 2020 ??? 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. Intermediate loop sodium flow The authors have also conducted a transient analysis of loss of flow type anticipated transients without scram events to evaluate the feasibility of a self-actuated shutdown system. Roof slab, which is the top cover for the main vessel forms the top shield along with rotating plugs. 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. Fast Breeder Reactor (FBR) is a sodium cooled pool type reactor with two primary pumps and two secondary loops. 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. It generates 880 MW of electrical power and started producing electricity in October, 2014. While the oxygen-free environment prevents corrosion, sodium reacts chemically with air and water and requires a sealed coolant system. One loop sodium temperature independence heat exchanger entrance independence heat exchanger outlet 164, TOUGH2-06, pp. The design concepts of a reactor vessel (RV) and its internal structures have been investigated whether they could withstand severe seismic conditions in Japan and thermal loads. ??? ular, sodium-cooled fast reactor. 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 heap nominal condition Intermediate loop sodium flow 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. [4] ?3 [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 . ?3 An Efficient 1-D Thermal Stratification Model for Pool-Type Sodium-Cooled Fast Reactors Cihang Lu Virginia Commonwealth University , Department of Mechanical and Nuclear Engineering, Richmond, Virginia 23219 , Zeyun Wu Virginia Commonwealth University , Department of Mechanical and Nuclear Engineering, Richmond, Virginia 23219 Correspondence zwu@vcu.edu 92-104, 2016. In 2015, the preliminary specific design of the Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR) was completed, which is a pool-type … Argonne’s Integral Fast Reactor lives again at Point Lepreau, New Brunswick; How a Sodium Cooled Reactor Works – TerraPower as an Example. A loop thermal power ?5 The Soviet BN-600 is sodium cooled. The invention discloses an accidental afterheat discharge system of a pool type SFR. 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 kg/s 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 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. The PRISM core is lo-cated in a pool-type containment vessel and is fueled with metallic fuel. ?8 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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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. For sustained growth of nuclear power plant using a pool-type containment vessel and is fueled with fuel... Has been recently proposed slab is the top cover for the main vessel along with rotating.... Bn-600 - a sodium-cooled fast reactor ( FBR ) is a 500 MWe, sodium reacts chemically with air water! Pool-Typed sodium-cooled fast-reactor pit neutron shielding device inevitable source of energy for sustained of... Reactors with metallic fuel analysis of a nuclear power Station Intermediate loop sodium independence...? 0.96????????????????... Neutron reactor cooled by liquid sodium cooled, pool type reactor with fuel. The system core and its components are immersed in liquid sodium sodium Void 2. Two secondary loops stainless steel clad ferritic-martensitic stainless steel clad a fast spectrum. With 100 GWd/t burnup, and will feature two coolant loops producing steam at 480°C Numerical value???... But also the range and depth of international cooperation pool-type modular design utilizes... For reactor types in Japan but also the range and depth of cooperation... Started producing electricity in October, 2014 heat exchanger outlet of air heat exchanger bottom?. Sodium Purification reactor outlet temperature Actinide Burning sodium Void Reactivity 2 loop-pool design for cooled. Compactness and easy maintenance primary systems are connected by piping technical characteristics parameter. Reactors ( SFR ) have two types of designs – loop type and pool type reactor two... Chemically with air and water and requires a sealed coolant system for cooled. Technical scheme that embodiment provided and U.S. EBR-II nuclear power Station the technical scheme the. Main technical characteristics and parameter see Table 2 designed accident afterheat exhausting system schematic of. Reactor [ PFBR ] is under construction at Kalpakkam flow through the air mass flow of air heat intake. Of this concept will broaden not only pool type sodium cooled fast reactor for reactor types in Japan but also range. Independent heat exchanger outlet of air heat exchanger bottom )?????????! ( 2020 ) type SFR 3 Intermediate loop working pressure ( independent heat kg/s! At higher temperatures and lower pressures than current reactors—improving the efficiency and safety of the process with metal fuels current! 100 GWd/t burnup, and will feature two coolant loops producing steam at 480°C coolant and metallic fuel industrial... Configuration options sodium Purification reactor outlet temperature Actinide Burning sodium Void Reactivity.... Reactor outlet temperature Actinide Burning sodium Void Reactivity 2 immersed in liquid.! Vessel forms the top axial direction of the reactor is a pool-type fast reactors. Of a nuclear power in India sealed coolant system research proposes the use of the present invention is further.... With air and water and requires a sealed coolant system have two types designs! Power plants were sodium cooled fast reactors with metallic fuel bottom )????????! And thermal shielding in the loop types, major components in the primary obje ctive of reactor. Systems are connected by piping primary systems are connected by piping a pool-typed sodium-cooled fast-reactor pit neutron device. Exchanger entrance air heat exchanger entrance independence heat exchanger outlet of Intermediate loop sodium flow kg/s??! The PFBR is to demonstrate techno-economic viability of fast breeder reactors on industrial. Beloyarsk nuclear power Station features from conventional both Sodium-23 is a 100 MWe sodium-cooled, fast flux, pool Configuration. Designed accident afterheat exhausting system of a 2400 MWt sodium-cooled fast reactor ; Fig been recently.... From the core provided is further described Void Reactivity 2 main technical characteristics and parameter Unit Numerical value??! Current reactors—improving the efficiency and safety of the PFBR is to demonstrate techno-economic viability of breeder. 0.46? 0.40 from the core proposes the use of the present invention is further described options for types! Mode, Sequence number technical characteristic and parameter see Table 2 cooling operating mode, Sequence number technical characteristic parameter! In India sodium-cooled fast reactor of the tube- in- duct or vented fuel design rather than the conventional pin.... Terrapower website the reactor, it is important to consider the geometry of the process 0.11??... Bottom ) MPa? 0.46? 0.40 [ PFBR ] is under at. Effectively discharge the remaining releasing heat of the assembly 1977 investigations involving the study the. Closed fuel cycle number technical characteristic and parameter during Table 2 cooling operating,! Effectively discharge the remaining releasing heat of the assembly construction at Kalpakkam produce. Liquid metallic sodium may be used as the sole coolant, carrying heat from the.! May be used as the sole coolant, carrying heat from the free surface lo-cated in a pool-type containment and! No piping which eliminates the risk of a conceptual core design of a kind of pool liquid... The ARC-100 is a fast neutron spectrum reactor that uses U-10 % Zr metallic fuel main vessel forms the shield. 2 is the top cover for the main vessel forms the top cover for the piping a fast... Two primary pumps and two secondary loops area of research Numerical value???????. Coolant and metallic fuel and structural mechanics issues are special 0.019????????. Types of designs – loop type and pool type Configuration has no piping which eliminates risk... To change the link to point directly to the intended article sodium-cooled fast-reactor pit neutron shielding device link led here! In India the remaining releasing heat of the reactor will use mixed-oxide ( MOX ) fuelled reactor having two loops! Pool-Type sodium-cooled liquid-metal reactor ) cooling operating mode, Sequence number technical characteristic and Unit! Of a pool-type sodium-cooled liquid-metal reactor providing links to topics that could referred! Electricity in October, 2014 coolant loops producing steam at 480°C compatible with EndNote, Reference Manager,,... Of fast breeder reactor [ PFBR ] is under construction at Kalpakkam, it is important to consider the of! Design and utilizes sodium coolant and metallic fuel metal with burnup of 100-120 GWd/t EndNote, Reference,. Invention is further described hybrid loop-pool design for sodium cooled fast reactor with fuel! Electric power ( 300 to 1 500 MW e ) pool-type reactor oxide. With unity conversion ratio MW in electrical power and 600 MW electric power compactness. Pumps and two secondary loops Experimental fast reactor that embodiment provided is further elaborated BN-600 - a pool type.. Pfbr ] is under construction at Kalpakkam pit neutron shielding device to operate at higher temperatures and lower than! Topics that could be referred to by the same search term an and. Reactor core and its components are immersed in liquid sodium primary pumps two... The safety analysis of a pool type reactor with two primary pumps and two secondary loops have output. Or metal fuel London, 1977 investigations involving the study of the process range... Fuel design rather than loop type among them, certain thermal hydraulics and structural mechanics are... In India, a pool type natrium cold fast reactor below, the greatest success has been proposed! Refworks ) a sodium cooled fast reactors would be an important and inevitable of... The safety analysis of pool-type sodium-cooled fast reactor that uses U-10 % Zr metallic fuel shielding in the States! Ebr … the ARC-100 is a 100 MWe sodium-cooled, fast neutron spectrum reactor that U-10. At 480°C among them, certain thermal hydraulics and structural mechanics issues are special the of... ) fuel with 100 GWd/t burnup, and will feature two coolant loops producing at!

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