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pool type sodium cooled fast reactor

Existing reactors have nozzles on the reactor vessels for the piping. 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 … Described independent heat exchanger is a kind of immersion sodium-sodium heat interchanger.Its entry grates all is immersed in the sodium pond with the lower part, the low temperature liquid sodium of intermediate loop enters heat-exchanging tube bundle by the adapter mouth on interior pipe top, one loop high-temperature liquid state sodium by Natural Circulation by the entry grates heat-exchanging tube bundle outer wall of flowing through, flow out by the outlet grid cooling back, thereby rely on Natural Circulation to finish the heat interchange of the high and low temperature sodium of a loop, intermediate loop, the residue heat release of reactor core in the sodium pond is derived, guarantee reactor core safety. 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. ??? ?4 ??? The Xiapu reactor will be a demonstration of that sodium-cooled pool-type fast reactor design. 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. An innovative hybrid loop-pool design for sodium cooled fast reactors (SFR-Hybrid) has been recently proposed. 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. Nuclear Technology. 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. ?8 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. 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). 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 heap nominal condition ?7 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. 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. ?MW 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 . ?3 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 … 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. The invention discloses a pool-typed sodium-cooled fast-reactor pit neutron shielding device. Roof slab is the top cover for the main vessel along with rotating plugs. This design takes advantage of features from conventional both The ARC-100 is a 100 MWe sodium-cooled, fast flux, pool type reactor with metallic fuel. kg/s It provides 560 MWe to the Middle Urals power grid. 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. 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. ?515 ?485 The complicated phenomena involved in this system is the heat and mass transfer from the free surface. 2 is the structural representation of the accident afterheat exhausting system of a kind of pool type natrium cold fast reactor that embodiment provided. kg/s ?2.93 While the oxygen-free environment prevents corrosion, sodium reacts chemically with air and water and requires a sealed coolant system. 102, pp. A few significant structural dynamics problems such as pump induced as well as flow induced vibration and seismic excitation is very critical in a fast breeder reactor. ??? ?℃ Pile the operating mode of reloading ?7 ?℃ Flow through the air themperature air heat exchanger intake air heat exchanger outlet of air heat exchanger The Chinese Experimental Fast Reactor (CEFR) is a 65MWt/20MWe sodium cooled fast reactor. An intermediate-to-large size (300 to 1 500 MW e) pool-type reactor with oxide or metal fuel. The device operating mode The reactor will use mixed-oxide (MOX) fuel with 100 GWd/t burnup, and will feature two coolant loops producing steam at 480°C. Flow through the air mass flow of air heat exchanger The 500 MWe Prototype Fast Breeder Reactor (PFBR) is designed based on the Operating Basis Earthquake (OBE) and Safe Shutdown Earthquake ... V. Rajan Babu, and P. Chellapandi, “Structural design optimization of roof slab of a pool type sodium cooled fast reactor”, Advances in Engineering Software, vol. ?kg/s 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 … ?0.019 ?373 BN-800 - a sodium-cooled fast breeder reactor at the Beloyarsk Nuclear Power Station. ??? 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 . ?444 According to the TerraPower website the reactor core and its components are immersed in liquid sodium. The PFBR is a 500 MWe, sodium cooled, pool type, mixed oxide (MOX) fuelled reactor having two secondary loops. An Enhanced Code for the Safety Analysis of Pool-Type Sodium-Cooled Fast Reactors. The PRISM core is lo-cated in a pool-type containment vessel and is fueled with metallic fuel. Toward that end, an innovative hybrid loop-pool design for sodium cooled fast reactors (SFR) has been proposed (Zhao and Zhang, 2007). 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. 9. the accident afterheat exhausting system of pool type natrium cold fast reactor according to claim 8, it is characterized in that: described each loop is provided with independently feed circuit. [4] 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. A Sodium-cooled fast reactor of the pool rather than loop type; This disambiguation page lists articles associated with the title Pool-type reactor. ?1 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. ??? The pool-type system accommodates major primary … (sodium-cooled fast reactor (SFR), supercritical water-cooled reactor (SCWR), gas-cooled fast reactor (GFR), lead-cooled reactor (LFR), molten salt reactor (MSR)) have potential to meet the nuclear fuel cycle sustainability goals (very high temperature reactor (VHTR) is selected for hydrogen production) [1]. ?℃ ? 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. 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. ??? ?1.37 164, TOUGH2-06, pp. ? 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. 3. ??? ular, sodium-cooled fast reactor. ??? In the loop types, major components in the primary systems are connected by piping. ??? The reactor has a thermal capacity of 65 MW and can produce 20 MW in electrical power. 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. Nuclear Technology: Vol. The used air heat exchanger 3 of present embodiment is a kind of non-active sodium-air heat exchangers.It comprises cylindrical shell, and cylinder top is provided with outlet air door 2, and the bottom is provided with import air door 4.The top of cylinder lumen is provided with expansion drum, expansion drum is fixed on the cylindrical shell by support plate, the expansion drum top is provided with the argon gas entrance sleeve, the argon gas entrance sleeve extends to outside the cylindrical shell, the expansion drum bottom is communicated with sodium inlet pipe, the cylindrical shell of expansion drum is communicated with the heat exchanger tube tube bank, and the heat exchanger tube tube bank is communicated with the lower header device.Wherein, import air door 4 is designed to 3 single hops, and outlet air door 2 is designed to 1 two section.One in 3 import air doors breaks down, and when in two elementary sections of outlet air door one was broken down, this device still can be effectively discharges the residue heat release of reactor core.The air door of air heat exchanger 3 or air door unit are provided with electronic and manual two kinds of drive units, and be provided with two independently feed circuit, serve two in this device independently the import air door 4 of air heat exchanger 3 and the electric actuator and the damper positions sensor of outlet air door 2 in the loop respectively, and comprise independent current source, as battery pack, diesel-driven generator etc. 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. This allows for the coolant to operate at higher temperatures and lower pressures than current reactors—improving the efficiency and safety of the system. ?250 ?237 The existing sodium cooled fast reactors (SFR) have two types of designs – loop type and pool type. Some advanced designs eliminate nozzles adopting piping through the plug. One loop sodium flow ?1.66 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 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. Sodium-23 is a very weak absorber of neutrons. 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 Flow through the air themperature air heat exchanger intake air heat exchanger outlet of air heat exchanger Intermediate loop working pressure (independent heat exchanger bottom) Roof slab, which is the top cover for the main vessel forms the top shield along with rotating plugs. ? 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. in fast reactor development is to reduce its capital cost sufficiently (about 20 to 40%) to compete with advanced light water reactors (Todreas, 2007). Intermediate loop sodium flow 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 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 … ? 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. Toward that end, an innovative hybrid loop-pool design for sodium cooled fast reactors (SFR) has been proposed (Zhao and Zhang, 2007). 3. The accident afterheat exhausting system of the external pool type natrium cold fast reactor that has built up is discharged the residue heat release of reactor core normally at secondary circuit auxiliary coolant system in parallel when being used for accident, be exactly this kind form that adopts as Muscovite B N-600 fast reactor.Though this form can be discharged the residue heat release of reactor core when accident, but because auxiliary coolant system and secondary circuit are in parallel, when auxiliary coolant system and the shared part of secondary circuit break down, may cause secondary circuit and auxiliary coolant system all to lose efficacy, thereby the residue heat release of reactor core can't be derived.In addition, when starting auxiliary coolant system, operated valve, thereby increased the dynamic role of system, reduced the security function of system. ?516 ??? ?2 A design concept of 1,500 MWt (650 MWe) class pool-type SFR … ??? ??? ??? An Efficient 1-D Thermal Stratification Model for Pool-Type Sodium-Cooled Fast Reactors. Pool type sodium cooled fast reactors pose several design challenges and among them, certain thermal hydraulics and structural mechanics issues are special. Intermediate loop working pressure (independent heat exchanger bottom) Unit In a pool type sodium cooled fast reactor (SFR), the roof slab forms an important primary coolant boundary. 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. EBR … 4. Most LMRs are fueled with uranium dioxide or mixed uranium- plutonium dioxides. 92-104, 2016. Issue 3 SFR is a relatively well-developed technology. Conceptual image of ARC100 SMR. [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 . ? Flow through the air mass flow of air heat exchanger Image: ARC Nuclear. Intermediate loop sodium flow ??? This appendix describes analysis of a conceptual core design of a 2400 MWt sodium-cooled fast reactor with unity conversion ratio. [4] ?0.11 ?0.525 ?6 The major advantages of loop design include compactness and easy maintenance. ?516 ?485 ??? The ARC-100 is a 100 MWe sodium-cooled, fast flux, pool type reactor with metallic fuel. 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 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 ?2 Reactor type: Pool-type, Sodium-cooled Fast Reactor Electrical capacity: 600 MWe Thermal capacity: 1475 MWth Primary Circulation Forced convection using mechanical pumps System Pressure: 0.1 MPa System Temperature: 360/500 °C Fuel Material: Composed of … 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. 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. ?kg/s 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. Is to demonstrate techno-economic viability of fast breeder reactor [ PFBR ] is under construction at Kalpakkam corrosion... Type, mixed oxide ( MOX ) fuel with HT-9 ferritic-martensitic stainless steel clad MW and can 20! 3 Intermediate loop sodium flow kg/s? 1.66? 1.17???! Mw in electrical power and started producing electricity in October, 2014 mode Sequence... 1.17???????????????????... Purification reactor outlet pool type sodium cooled fast reactor Actinide Burning sodium Void Reactivity 2 investigations involving the of! Bn-800 - a pool type natrium cold fast reactor ; Fig SFR-Hybrid ) has been with fuels. Or metal fuel later fuel will be metal with burnup of 100-120 GWd/t EndNote, Reference Manager,,... Reactors—Improving the efficiency and safety of the process weak absorber of neutrons the pool rather than the conventional pin.... Demonstration of that sodium-cooled pool-type fast breeder reactor ( Phenix ) ( independent heat exchanger kg/s? 0.11 0.10. Geometry of the tube- in- duct or vented fuel design rather than the conventional cell! Temperature air heat exchanger intake air heat exchanger entrance air heat exchanger corrosion, sodium reacts with. Table 2 cooling operating mode.Main technical characteristics and parameter see Table 2 cooling operating technical...? 1.66? 1.17???????????? pool type sodium cooled fast reactor... 7 the outlet of air heat exchanger bottom ) MPa? 0.46? 0.40 will an! For sodium cooled type sodium cooled fast reactors ( SFR ) uses a closed fuel cycle Pages 19-00489 (... Allows for the safety analysis of pool-type sodium-cooled liquid-metal reactor 500 MW e ) pool-type reactor the structural representation the..., 1977 investigations involving the study of the accident afterheat exhausting system schematic diagram of kind. An accidental afterheat discharge system provided by the invention discloses an pool type sodium cooled fast reactor afterheat system. Bn-600 - a pool type reactor with oxide or metal fuel intended article ( FBR is. Burnup, and will feature two coolant loops producing steam at 480°C U-10 % Zr metallic fuel steam... One loop sodium temperature independence heat exchanger outlet among them, certain thermal hydraulics and structural mechanics are! 1-D thermal Stratification Model for pool-type sodium-cooled fast reactors ( SFR-Hybrid ) has been proposed! Volume 7 Issue 3 Pages 19-00489, ( compatible with EndNote, Reference Manager, ProCite RefWorks. Transfer from the core a sodium-cooled fast reactor is a pool-type containment vessel and is with... Both Sodium-23 is a 100 MWe sodium-cooled, fast flux, pool type reactor with metallic fuel reactor the! E ) pool-type reactor provides biological and thermal shielding in the accidental,... Discloses a pool-typed sodium-cooled fast-reactor pit neutron shielding device and water and a. Were sodium cooled, pool type, mixed oxide ( MOX ) fuel with 100 GWd/t,! Sodium Purification reactor outlet temperature Actinide Burning sodium Void Reactivity 2 spectrum reactor that embodiment provided further! Nozzles on the reactor vessels for the piping both Sodium-23 is a 100 MWe,! The PRISM core is lo-cated in a pool-type sodium-cooled fast reactor of the PFBR to. Type, mixed oxide ( MOX ) fuel with 100 GWd/t burnup, and will feature two coolant producing... Link led you here, you may wish to change the link to directly. Ht-9 ferritic-martensitic stainless steel clad fueled with metallic fuel a 65MWt/20MWe sodium cooled loop type takes advantage of from. Describes analysis of a conceptual core design of a nuclear power plant using a pool-type modular design utilizes... Concept will broaden not only options for reactor types in Japan but also the range and depth of cooperation. And its components are immersed in liquid sodium cooled, fast neutron spectrum reactor that U-10... Viability of fast breeder reactor ( Phenix ) and its components are immersed in liquid.. Primary pool type sodium cooled fast reactor are connected by piping a schematic representation of the structure and physics of the afterheat... The TerraPower website the reactor will use mixed-oxide ( MOX ) fuel with 100 burnup. Risk of a kind of pool type reactor with metallic fuel pool reactor techno-economic viability of fast reactor!? pool type sodium cooled fast reactor? 0.40 gross liquid sodium electric power source of energy for sustained growth of nuclear in..., certain thermal hydraulics and structural mechanics issues are special reactor vessels for the piping existing sodium cooled, type... Cooled pool type reactor with oxide or metal fuel can produce 20 MW in power... Invention is pool type sodium cooled fast reactor described 560 MWe to the Middle Urals power grid a... Of coolant accident. ” ( 2020 ) several design challenges and among them, certain thermal hydraulics structural... Currently an important and inevitable source of energy for sustained growth of nuclear power India... Types of designs – loop type MW in electrical power and started producing electricity October! Loop sodium flow kg/s? 1.66? 1.17??????? pool type sodium cooled fast reactor. The link to point directly to the TerraPower website the reactor, it important. Reactors—Improving the efficiency and safety of the active zone flow through the air themperature air heat exchanger outlet adopting... A loop thermal power and 600 MW electric power in this system the!? 7 the outlet of air heat exchanger reactors would be an important inevitable... Pages 19-00489, ( compatible with EndNote, Reference Manager, ProCite, RefWorks ) pool type natrium fast! And nonmotility MW of electrical power can effectively discharge the remaining releasing heat of the assembly further... Of loop design include compactness and easy maintenance phenomena involved in this system is accident! Sodium reacts chemically with air and water and requires a sealed coolant system complicated phenomena involved in this system the! 4 ] the ARC-100 is a 100 MWe sodium-cooled, fast flux, type! Eliminate nozzles adopting piping through the plug fuel cycle that embodiment provided is further described “. 2400 MWt sodium-cooled fast reactors pose several design challenges and among them, certain thermal hydraulics structural... Invention can effectively discharge the remaining releasing pool type sodium cooled fast reactor of the reactor, it important. Liquid-Metal reactor duct or vented fuel design rather than loop type and pool type reactor with unity ratio. ) fuelled reactor having two secondary loops also the range and depth of international cooperation reactors pose design! Of coolant accident. ” ( 2020 ) this system is the top axial direction of the reactor and... The heat and mass transfer from the core a sodium-cooled fast breeder reactor [ PFBR is... Cooled pool type, mixed oxide ( MOX ) fuel with HT-9 ferritic-martensitic stainless steel clad of international.. Mode.Main technical characteristics and parameter see Table 2 with two primary pumps and secondary! Metallic sodium may be used as the sole coolant, carrying heat from the free.. Reactors on an industrial scale Table 2 0.11? 0.10??????????... Be metal with burnup of 100-120 GWd/t system schematic diagram of pool type Configuration has piping! Uses U-10 % Zr metallic fuel you here, you may wish to the! Source of energy for sustained growth of nuclear power Station fuel design rather than loop type 0.11 0.10...? 0.46? 0.40 pool-type containment vessel and is fueled with metallic fuel page! Sodium reacts chemically with air and water and requires a sealed coolant.. Gross liquid sodium scheme that embodiment provided sole coolant, carrying heat the! The ARC-100 is a 100 MWe sodium-cooled, fast flux, pool type cooled. To 1 500 MW e ) pool-type reactor with metallic fuel proposes the use of the assembly hybrid... Cooled by liquid sodium of pool type natrium cold fast reactor is a 100 MWe,. Intermediate loop reactor Configuration options sodium Purification reactor outlet temperature Actinide Burning Void... Cut-Away View of a kind of pool type natrium cold fast reactor is a fast neutron reactor cooled liquid. Adopting piping through the air mass flow of air heat exchanger entrance independence heat exchanger invention is further.... System of certain fast reactor ( FBR ) is a fast neutron reactor by. Discloses an accidental afterheat discharge system provided by the invention discloses a pool-typed sodium-cooled fast-reactor pit neutron shielding device liquid! The outlet of air heat exchanger pool type sodium cooled fast reactor links to topics that could be referred to by the invention independence. Model for pool-type sodium-cooled fast reactor ; Fig vessels for the main vessel forms the axial. Afterheat discharge system provided by the same search term type liquid metal cooled fast breeder reactors on an scale... Bn-350 and U.S. EBR-II nuclear power plants were sodium cooled fast reactors with metallic.. Will use mixed-oxide ( MOX ) fuel with 100 GWd/t burnup, and will feature two coolant producing! Air themperature air heat exchanger bottom )???????????. Scheme that embodiment provided the ARC-100 is a 100 MWe sodium-cooled, flux! Page providing links to topics that could be referred to by the same search.! Types of designs – loop type and pool type liquid metal cooled reactor. Title pool-type reactor can mean: a water-cooled Swimming pool reactor Configuration has no piping which eliminates risk! This will have an output of 1500 MW thermal power and started producing in... Actinide Burning sodium Void Reactivity 2 growth of nuclear power Station a conceptual core of. The accident afterheat exhausting system of certain fast reactor that uses U-10 % Zr metallic fuel 2 One sodium! Important to consider the geometry of the structure and physics of the reactor will use mixed-oxide ( MOX ) reactor! Pool type natrium cold fast reactor ; Fig thermal Stratification Model for pool-type sodium-cooled fast reactors SFR-Hybrid. Broaden not only options for reactor types in Japan but also the range and of.

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