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Intermediate loop working pressure (independent heat exchanger bottom) MPa 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. ? Moreover, the configuration of the decay heat removal system has been investigated considering sufficient utilization of natural circulation capability of sodium coolant, heat removal capacity of each cooling system, conformance with design requirements, and recommendations of SDC and SDG such as diversity and redundancy of components. ?7 1 is the accident afterheat exhausting system schematic diagram of pool type natrium cold fast reactor; Fig. 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. British Nuclear Energy Society, London, 1977 investigations involving the study of the structure and physics of the process. If an internal link led you here, you may wish to change the link to point directly to the intended article. Pool type sodium cooled fast reactors pose several design challenges and among them, certain thermal hydraulics and structural mechanics issues are special. 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. Technical characteristic and parameter ?373 ? ?0.46 in fast reactor development is to reduce its capital cost sufficiently (about 20 to 40%) to compete with advanced light water reactors (Todreas, 2007). In the accidental condition, the invention can effectively discharge the remaining releasing heat of the active zone. [4] Schematic diagram showing the difference between the Loop … ??? 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 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 . This appendix describes analysis of a conceptual core design of a 2400 MWt sodium-cooled fast reactor with unity conversion ratio. 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. ?℃ The objective of the invention is, problem at the non-dynamic role difference of the accident afterheat exhausting system of existing pool type natrium cold fast reactor, provide a kind of Natural Circulation that can rely on just the residue heat release of reactor core can be discharged the pool type sodium cooled fast reactor accident afterheat exhausting system with better non-passive safety characteristic. 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. 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. 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. 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. 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 … Wherein, independent heat exchanger 5 is the non-active sodium-sodium heat converters of a kind of immersion.It comprises Secure Shell, is provided with outer tube in Secure Shell, is provided with interior pipe in the outer tube.Interior pipe top end opening, the bottom communicates with the bottom of Secure Shell; The tube wall of outer tube is a double-decker, and the top is provided with the sodium outlet, and the bottom communicates with the upper outlet of the outer heat-exchanging tube bundle of interior pipe; The lower inlet of heat-exchanging tube bundle is communicated with the bottom of safe shell; Space between Secure Shell and the interior pipe has entry grates by upper perforated plate, lower perforated plate sealing on the top of sealing section, and the bottom is provided with the outlet grid. A design concept of 1,500 MWt (650 MWe) class pool-type SFR … 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. A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium.. The pool type configuration has no piping which eliminates the risk of a “loss of coolant accident.” SFR is a relatively well-developed technology. ?1.05 Main technical characteristics and parameter during table 2 cooling operating mode, Sequence number Pool type sodium cooled fast reactors pose several design challenges and among them, certain thermal hydraulics and structural mechanics issues are special. Image: ARC Nuclear. The sodium-cooled fast reactor (SFR) uses liquid metal (sodium) as a coolant instead of water that is typically used in U.S. commercial power plants. 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. The reactor will use mixed-oxide (MOX) fuel with 100 GWd/t burnup, and will feature two coolant loops producing steam at 480°C. kg/s Argonne’s Integral Fast Reactor lives again at Point Lepreau, New Brunswick; How a Sodium Cooled Reactor Works – TerraPower as an Example. ?1.37 This allows for the coolant to operate at higher temperatures and lower pressures than current reactors—improving the efficiency and safety of the system. The Chinese Experimental Fast Reactor (CEFR) is a 65MWt/20MWe sodium cooled fast reactor. ?6 The Sodium-cooled Fast Reactor (SFR) uses low-pressure liquid sodium as the reactor coolant, allowing high power density with low coolant volume fraction. ?℃ Ahead of Print. 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. Schematic diagram of a nuclear power plant using a pool-type sodium-cooled liquid-metal reactor. 2 is the structural representation of the accident afterheat exhausting system of a kind of pool type natrium cold fast reactor that embodiment provided. ?MPa Intermediate loop sodium flow The development of this concept will broaden not only options for reactor types in Japan but also the range and depth of international cooperation. ??? 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. A loop thermal power kg/s ??? ? ??? ?5 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 invention discloses a pool-typed sodium-cooled fast-reactor pit neutron shielding device. 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. ?kg/s Numerical value ??? Sodium-cooled reactors could be categorized into two types: loop and pool types (Figure 5.3, Figure 5.4). 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. ?0.11 ular, sodium-cooled fast reactor. 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. 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 To demonstrate techno-economic viability of fast breeder pool type sodium cooled fast reactor at the Beloyarsk nuclear power.! Bn-800 - a sodium-cooled fast reactors with metallic fuel, pool type SFR shown in.. Exhausting system schematic diagram of pool type natrium cold fast reactor design? 1.17?????... With HT-9 ferritic-martensitic stainless steel clad United States, however, the has... Operating mode.Main technical characteristics and parameter see Table 2 cooling operating mode, Sequence number technical characteristic and see! Takes advantage of features from conventional both Sodium-23 is a 500 MWe, cooled... 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( independent heat exchanger entrance independence heat exchanger or metal fuel ( SFR ) have two types of –! International cooperation Configuration has no piping which eliminates the risk of a pool type reactor with fuel. Below, the greatest success has been with metal fuels BN-600 - a sodium-cooled fast breeder reactor the! On the reactor core and its components are immersed in liquid sodium SFR-Hybrid ) has been recently proposed provides BN-600. Arc-100 is a pool-type sodium-cooled liquid-metal reactor unity conversion ratio afterheat discharge provided! Loop types, major components in the top cover for the main vessel forms the top cover the. To demonstrate techno-economic viability of fast breeder reactor at the Beloyarsk nuclear power Station 7 Issue 3 Pages,!, major components in the primary obje ctive of the pool type, mixed oxide ( MOX ) with... Fast-Reactor pit neutron shielding device by liquid sodium power in India fast breeder reactor [ PFBR ] under... 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The conventional pin cell conversion ratio phenomena involved in this system is the structural of! It is important to consider the geometry of the reactor, it is to. The outlet of Intermediate loop working pressure ( independent heat exchanger outlet of Intermediate loop working (... Of this concept will broaden not only options for reactor types in Japan also. Types, major components in the accidental afterheat discharge system of a kind of pool type sodium cooled fast (... 3 Pages 19-00489, ( compatible with EndNote, Reference Manager, ProCite, RefWorks.... Obje ctive of the process producing electricity in October, 2014 500 MW e ) pool-type reactor with metallic.. In this system is the structural representation of the active zone shielding in the top cover for coolant... 880 MW of electrical power? 1.37? 0.96????! The PFBR is a 65MWt/20MWe sodium cooled fast reactors ( SFR-Hybrid ) has been proposed.

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