专利汇可以提供SYSTEM FOR PASSIVELY REMOVING HEAT FROM INSIDE A CONTAINMENT SHELL专利检索,专利查询,专利分析的服务。并且The invention relates generally to the nuclear energy field, and more particularly to pressurized water reactor containment internal passive heat removal systems (C PHRS), and is designed for reactor containment cooling by natural circulation of the cooling liquid (water) in the system circuit. The technical result of the invention is increase of heat removal efficiency, flow stability in the circuit and, consequently, system operation reliability. The system has at least one cooling water circulation circuit comprising a heat exchanger located inside the containment and including an upper header and a lower header interconnected by heat-exchange tubes, a riser pipeline and a downtake pipeline connected to the heat exchanger, a cooling water supply tank located above the heat exchanger outside the containment and connected to the downtake pipeline, a steam relief valve connected to the riser pipeline and located in the water supply tank and hydraulically connected to the latter. The upper header and the lower header of the heat exchanger are divided into heat-exchange tube sections on the assumption that: L/D ≤ 20, where L is the header section length, D is the header bore.,下面是SYSTEM FOR PASSIVELY REMOVING HEAT FROM INSIDE A CONTAINMENT SHELL专利的具体信息内容。
The invention relates generally to the nuclear energy field, and more particularly to pressurized water reactor containment internal passive heat removal systems (C PHRS), and is designed for reactor containment cooling by natural circulation of the cooling liquid (water) in the system circuit.
According to the background of the invention, there are numerous designs of reactor containment heat removal systems based on natural heat circulation.
Russian patent
Russian patent
The closest analog of the claimed invention is the PHRS system disclosed in Russian utility model patent
The disadvantage of the said devices is potential water hammer in the system.
The purpose of the invention is to provide a system for efficient heat removal from the reactor containment.
The technical result of the invention is increase of heat removal efficiency, flow stability in the circuit (no water hammer) and, consequently, system operation reliability.
The said technical result is achieved owing to the fact that the pressurized water reactor containment internal passive heat removal system with at least one cooling water circulation circuit comprises a heat exchanger located inside the containment and including an upper header and a lower header interconnected by heat-exchange tubes, a riser pipeline and a downtake pipeline connected to the heat exchanger, a cooling water supply tank located above the heat exchanger outside the containment and connected to the downtake pipeline, a steam relief valve connected to the riser pipeline and located in the water supply tank and hydraulically connected to the latter. The upper header and the lower header of the heat exchanger are divided into heat-exchange tube sections on the assumption that:
the riser pipeline design provides the minimum riser section height hrs to meet the following criterion:
The above technical result is also achieved in specific options of the invention owing to the fact that:
is the Schmidt number,
For the purposes of this application, the riser section means the portion of the riser pipeline where the coolant is a steam-water (two-phase) mixture with mean mass steam quality x. The section is referred to as "riser" as it makes a major contribution to development of natural circulation in the circuit and determines its intensity.
The experiments conducted show that the above system parameter correlations provide the most efficient heat removal without water hammering or coolant mass-flow rate perturbation due to selection of the best system geometry: the correlation between the length and bore of the heat exchanger header sections, length of the circulation circuit riser section, height of the heat-exchange tubes and optimized arrangement of the system heat exchangers in the containment.
The correlation of the section length and bore of the heat exchanger headers is selected so as to minimize the non-uniformity of coolant flow distribution among the heat exchanger tubes, i.e. to reduce the so-called "header effect". The uniform distribution of flow in the tubing is one of the main conditions for improved energy efficiency and performance of heat exchangers. One of the methods used to improve coolant distribution among the header heat exchanger channels is pressure loss reduction of the medium flow in the header. This is achieved by reducing the header length and increasing its bore within the device manufacturing process capabilities and other design features. For headers meting the L/D ≤ 20 criterion, pressure loss along the header length is minimal, and distribution of coolant flows among the heat exchanger tubes is the most uniform. When the said criterion is exceeded, the uniformity of medium distribution among the heat exchanger channels degrades, which results in the coolant mass flow instability and perturbation and, subsequently, reduced heat output of the heat exchanger.
The design of the invention is illustrated by drawings, where:
The claimed system is a combination of cooling water circulation circuits. In the preferable embodiment of the invention, the claimed system consists of four completely independent channels, each comprising four such circulation circuits.
The circulation circuit (
The upper header (2) and the lower header (3) of the heat exchanger are divided into heat-exchange tube sections on the assumption that:
the riser pipeline design provides the minimum riser section height hrs to meet the following criterion:
The heat exchanger section has a single-row vertical bundle. It is preferable that the spacing between any adjacent section tubes meets the equivalent plane wall criterion.
In the preferable embodiment of the invention, the heat-exchange tube height ensures that the criterion of the turbulent convection on the heat exchanger outer surface is met, namely:
is the Schmidt number,
The riser pipeline from the upper heat exchanger section headers to the steam relief valve has an upward inclination to the angle of a least 10° in relation to the horizontal line, except for certain sections with an inclination less than 10°, having length Lsec1 and bore Dsec1, meeting the following criterion: Lsec1/Dsec1 ≤ 10.
The downtake pipeline has a downward inclination to the angle of a least 10° in relation to the horizontal line, with the exception of certain sections with an inclination less than 10°, length Lsec2 and bore Dsec2, meeting the following criterion: Lsec2/Dsec2 ≤ 10.
In the specific embodiment of the invention for the Leningrad-2 NPP reactor plant, the heat exchangers (1) of the circuits are located along the perimeter on the containment inner wall above elevation 49.3 m. Each heat exchanger has a heat-exchange area of 75 m2. The heat-exchange bundle height is 5 m and is built up by 38×3 mm vertical tubes. The total heat-exchange area of each channel amounts to 300 m2. The length (L) of the upper and lower sections of the heat exchanger headers equals 2,755 mm. The outer/inner diameter (D) of the upper header is 219/195 mm, the one of the lower header is 194/174 mm.
The system heat output is selected so as to reduce and maintain pressure in the containment inside pressure within the design limits during beyond design basis accidents of reactors, including those involving severe core damage.
Isolating valves (9) and (10) designed for isolation of the heat exchanger (1) in the event of its leakage are mounted on the riser pipeline (5) and downtake pipeline (6). To prevent overpressurization of the C PHRS circuits in case of emergency closing of the isolating valves, safety valves (not shown) are installed to discharge fluid below the tank (7) level.
The isolating and safety valves are located in the reactor building envelope annulus compartments at elevation +54.45 m.
The claimed system operation is based on coolant natural circulation and requires no startup actions. Heat energy is removed from the containment by steam condensation from the steam-air mixture on the outer surface of the heat exchanger (1) from where it is transferred to the water supply tank (7) by means of natural circulation. Heat is ultimately removed from the water supply tank to the ultimate heat sink by evaporation of the water in the tank. The coolant is supplied from the steam relief valve (8) to the cooling water supply tank (7), followed by the cooled coolant (water) return to the heat exchanger (1) through the downtake pipeline (6). Thus, heat energy is transferred from the containment internal volume to the ultimate heat sink, the environment, by means of evaporation of the water in the tank (7) using the circulation circuit.
For experimental justification of the proposed system design efficiency, a significant amount of experimental work has been performed on several experimental setups.
Research has been performed on a full-scale model of the C PHRS cooling circuit installed on the JSC "Afrikantov OKBM" test stand. The C PHRS circuit model included a heat-exchanger-condenser model, operational pipelines located in the containment model tank, and a operational steam relief valve located in the water supply tank.
The heat removal capacity of the tested cooling circuit and parameters of the steam-gas medium in the tank are approximated to the actual reactor accident conditions of the operational system to the maximum extent. Therefore, with the geometry and parameters of the C PHRS cooling circuit practically comparable to the full-scale cooling circuit design, the research results obtained for the C PHRS cooling circuit model are representative and may be applied to the operational C PHRS cooling circuit.
The tests performed on the full-scale C PHRS cooling circuit loop shows that at the maximum cooling water temperature of 100 °C in the cooling water tank, and the specified design capacity per cooling circuit loop, the pressure in the tank will not exceed the design limit pressure of 500 kPa.
The full-scale C PHRS cooling circuit model tests performed show that the circuit design parameters are met both in terms of heat removal efficiency and circuit flow stability. Within the whole range of cooling circuit operation (power operation from the initial state to water boiling), no water hammering in the tank or vibration of the elements and structures of the tested circuit were observed that could affect its operability.
Therefore, the claimed system allows to maintain the pressure under the containment below the design level without operator's intervention for a long period of time and within the whole range of beyond design basis accidents involving release of mass and energy under the containment.
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