CN112069619A - Hydraulic performance optimization design method for lead-cooled fast reactor nuclear main pump - Google Patents

Hydraulic performance optimization design method for lead-cooled fast reactor nuclear main pump Download PDF

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CN112069619A
CN112069619A CN202010926369.0A CN202010926369A CN112069619A CN 112069619 A CN112069619 A CN 112069619A CN 202010926369 A CN202010926369 A CN 202010926369A CN 112069619 A CN112069619 A CN 112069619A
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pump
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lead
radius
inlet
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李良星
张双雷
张拯政
王凯琳
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Xian Jiaotong University
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Abstract

The invention discloses a hydraulic performance optimization design method of a lead-cooled fast reactor nuclear main pump, which is used for optimizing the radius R of a pump shell under the condition of meeting the given flow and liftsRadius of pump shaft RZAnd the rotating speed n, determining the optimal design of the pump, ensuring the minimum inflow speed of the coolant at the inlet and outlet of the main pump and the moving blade, and screening out the lowest coolant at the inlet flow speed of the moving blade and the inlet and outlet speed of the main pump. Because the corrosion speed of the lead-based coolant to the structural material of the pump body is related to the flow velocity, the axial flow nuclear main pump designed by the method can reduce the corrosion of the pump shell caused by the high outlet flow velocity of the coolant.

Description

Hydraulic performance optimization design method for lead-cooled fast reactor nuclear main pump
Technical Field
The invention relates to a hydraulic performance optimization design method of a lead-cooled fast reactor nuclear main pump, which is applied to the technical field of lead-cooled fast reactor design and provides technical support for the design of the lead-cooled fast reactor main pump.
Background
Lead-cooled fast reactors (LFRs) have proven to be one of the most promising fourth generation reactors, with neutron economy, thermohydraulics and safety properties. The design of a lead-based fast reactor main pump as a key component of a main loop is receiving more and more attention of researchers.
For example, the documents "Design by the experimental and CFD analysis of a multi-blade screw pump for a Generation IV LFR", "clear Engineering and Design,2016(297),276 and 290" Design a multi-blade screw pump as a main pump, which is considered a feasible choice by theoretical analysis and computational analysis and provides a feasible concept Design for European advanced demonstration express (ALFRED).
For example, Jaesik K, reproduction K, development of innovative fresh-integrated coolant design concept for a small modular lead fresh reactor J, International Journal of Energy Research,2018,42, proposes a magnetohydrodynamic coolant circulation system applicable to small modular lead-based fast reactors. The system is similar to the working principle of an electromagnetic pump, and utilizes the interaction of a magnetic field and current in coolant in a primary loop of a lead-cooled fast reactor to push lead-based alloy in the primary loop of a small module stack to generate directional motion, so that the forced circulation flow of the coolant is realized. But electromagnetic pumps are less efficient than mechanical pumps, have low pressures and low operating temperatures. However, from the viewpoint of dealing with accident conditions, the traditional mechanical pump has a higher safety margin than the electromagnetic pump.
For example, Beznosov, A.V., Lvov, A.V., Bokov, P.A., Bokova, T.A., & Razin, V.A. Experimental students inter the requirements of the axial lead compressor pump performance on the impeller compressor parameters and Technology,2017, 3(2),141-144. the influence of the axial flow liquid lead pump on the hydraulic performance and efficiency of the liquid lead pump by using different numbers of 3, 4, 6 and 8 blades in the working environment of 440-500 ℃ is experimentally researched, and the influence of different installation angles of the blades in the range of 9-43 ℃ on the hydraulic performance of the liquid lead pump is also researched. However, the corrosion of the pump body material caused by the high and low flow rate is not considered, and the low flow rate design aiming at reducing the corrosion of the coolant to the pump body is lacked.
Chinese patent application 201710041306.5 discloses a lead bismuth alloy bubble pump circulation capability experiment system and an experiment method thereof; chinese patent application 201920915659.8 discloses a vertical mixed flow pump for a primary circuit of a lead-bismuth reactor; chinese patent application 201920916210.3 discloses a vertical centrifugal pump for a primary circuit of a lead-bismuth reactor, which adopts a centrifugal impeller and a non-core-pulling type structure. None of the above patents address the optimization design of the main pump low flow rate to reduce the coolant erosion effect on the pump body.
Disclosure of Invention
The invention provides a hydraulic performance optimization design method of a lead-cooled fast reactor nuclear main pump, which aims to meet the requirement of low flow rate of a coolant in the lead-cooled fast reactor primary nuclear main pump and reduce corrosion of a lead-based coolant to a pump body material. The axial-flow pump designed by the method of the invention has the advantages of stable operation under the given flow and lift, minimum coolant inlet flow velocity at the moving blade and the corresponding inlet and outlet speed of the main pump, low coolant outlet flow velocity and small erosion on the wall surface of the pump body.
The purpose of the invention is realized by the following technical scheme:
a hydraulic performance optimization design method for a lead-cooled fast reactor nuclear main pump meets a given design flow QvAnd the pump shell radius R under the condition of the head HsRadius of pump shaft RZAnd the rotating speed n to obtain the optimal solution to determine the optimal design parameters of the pump and ensure the inlet flow velocity V of the coolant at the moving blade1And the corresponding speed of the inlet and the outlet of the main pump is minimum; wherein the optimal combination of the three variables is determined by the following conditions: the arcsine function value of the liquid flow angle at the outlet of the moving blade is more than 0; radius of pump shaft RZSmaller than the radius of the hub, i.e. the radius R of the pump casings(ii) a Radius R of pump casingsRadius of pump shaft RzThe three parameter values of the rotating speed n are all larger than 0; radius R of pump casingsRadius of pump shaft RzThree parameter values of rotating speed n and inlet flow velocity V1The constraint relationship of (1) is as follows:
Figure BDA0002668555260000031
wherein: etav-the lead based pump volume factor is the ratio of the actual flow to the theoretical flow;
Figure BDA0002668555260000032
the blade displacement coefficient is the ratio of the actual flow cross-sectional area to the flow cross-sectional area of the flow channel without considering the blade thickness;
the design of the moving blades and the guide blades adopts a plane cascade theory, and the flow channel of the lead bismuth pump is divided into a plurality of coaxial cylindrical flow surfaces;
axial velocity v of moving blade corresponding to inlet on single cylindrical flow surfacem1And axial velocity v of the outletm2Is obtained by the following formula, wherein AflowThe cross-sectional flow area of the cylindrical flow passage in the pump,
Figure BDA0002668555260000041
radius R of pump casingsRadius of pump shaft RzAfter the rotating speed n is determined, the relative circumferential component speed u of the pump shaft side can be obtained, and the absolute velocity circumferential component v of the moving blade inlet is accelerated because the lead-based alloy of the moving blade inlet does not act on the moving bladeu1Neglecting the size, taking the value of 0, and considering the circumferential component v of the absolute velocity of the moving blade outlet in the practical optimization processu2And (3) performing linear correction:
Figure BDA0002668555260000042
in the formula: h-theoretical design head, vu2The absolute speed circumferential component of the outlet of the moving blade, xi is a correction coefficient, and the value is taken from the pump shaft to the pump shell according to the linearity: 0.9 to 1.1;
inlet flow angle beta of moving blades at corresponding cylindrical flow surface1And outlet flow angle beta2Determined by the following equation:
Figure BDA0002668555260000043
inlet angle alpha of guide vane3Determined by the following equation:
Figure BDA0002668555260000044
α3=α3∞+Δα
α3∞for theoretical inlet angle, Δ α guide vane inlet attack angle, guide vane function to eliminate velocity ringing at the moving vane outlet and reduce flow velocity of lead-based coolant, it is desirable that the lead-based coolant be able to flow out in the axial direction after exiting the guide vane, where guide vane outlet angle α4Directly taking 90 degrees;
the pitch between the moving blades is t, the number of the moving blades of the lead-based pump is Z, and
t=Dnπ/Z
Dn-the nth layer of cylindrical flow surface diameter;
length l of moving blade airfoil
Figure BDA0002668555260000051
K is a calculation proportionality coefficient;
the width W of the flow passage in the guide vane area is taken as the radius R of the pump shellsMinus pump shaft radius RzLength l of guide vane profilecDetermined by the following equation:
Figure BDA0002668555260000052
the wrap angle of the moving blade is 70-90 degrees, the setting angle of the guide blade outlet is 90 degrees, the thickness of the impeller blade is 5-7mm, and the thickness of the guide blade is 4-6 mm.
Preferably, the lead-based pump volume coefficient ηvTake 0.95.
Preferably, the guide vane inlet angle of attack Δ α is in the range of 0 ° to 4 °.
Preferably, the value of the calculation proportionality coefficient K is 1.3-1.4.
Compared with the prior art, the invention has the following advantages:
for a given flow and lift, the pump casing radius RsRadius of pump shaft RZAnd the rotating speed n to obtain the optimal solution, determine the optimal design of the pump and ensure the inflow velocity V of the coolant at the moving blade1And (3) minimum, screening out the lowest coolant moving blade inlet flow velocity and the corresponding inlet and outlet speed of the main pump. Because the corrosion speed of the lead-based coolant to the structural material of the pump body is related to the flow velocity, the axial flow nuclear main pump designed by the method can reduce the corrosion of the pump shell caused by the high outlet flow velocity of the coolant.
Drawings
Fig. 1 is a two-dimensional planar cascade diagram of a moving blade obtained by spreading a cylindrical surface into a plane along a generatrix of a moving blade design example based on a planar cascade theory.
Fig. 2 is a two-dimensional plane cascade diagram of a guide vane obtained by spreading a cylindrical surface into a plane along a generatrix of a guide vane design example based on a plane cascade theory.
Detailed Description
The present invention will be described in detail below with reference to the accompanying drawings and specific embodiments.
The overall flow direction of the lead-based coolant in the main pump is generally axial in and out, but within the flow passage components (moving and guide vanes) of the main pump, the rotation of the vanes exerts a force on the fluid, causing the flow of the liquid metal coolant at this point to be a complex three-dimensional flow. When designing the flow passage component of the main pump, due to the particularity of the cylindrical structure of the axial flow pump, in order to simplify the complicated spatial flow of the fluid in the region, it is generally assumed that no flow in the radial direction exists in the fluid inside the flow passage component, only flows in the axial direction and the circumferential direction exist in the fluid inside the flow passage component, and the flows of the fluid on the respective cylindrical surfaces are not related, i.e. the independence of the cylindrical layers is assumed. By this assumption, the complicated three-dimensional flow in the axial flow pump can be simplified to the study of the flow on the cylindrical surface.
Flow in the pump according to the assumption of independence of the cylindrical layerThe channel can be divided into a plurality of coaxial cylindrical flow surfaces, and the cylindrical surfaces are unfolded into planes along the generatrices of the cylindrical flow surfaces, so that a two-dimensional plane blade grid of the blade is obtained and the design is unfolded. Fig. 1 and 2 show shapes of a design example of a moving blade and a guide blade based on the planar cascade theory, respectively. As shown in fig. 1 and 2: 1 is the moving blade outlet flow angle; 2 is the moving blade inlet flow angle; 4 is the guide vane outlet flow angle; 5 is the guide vane inlet flow angle; five cylindrical flow surfaces (L) are cut in the flow passages of the moving blades and the guide blades1-L5). Alpha (angle between absolute velocity and peripheral velocity), beta (angle between relative velocity and peripheral velocity), l (vane length), H for each flow surfacet(blade height), vm1、vm2(axial velocities of inlet and outlet of moving blade), relative circumferential speeds u and t (inter-blade pitch) of pump shaft side, and beta1、β2(inlet and outlet flow angle), alpha3(inlet angle of guide vane), guide vane profile length lcThe calculation methods of (a) and (b) are the same and can be obtained by the following methods. The wrap angle of the impeller blade is 70-90 degrees. The setting angle of the guide vane outlet is 90 degrees. Fixing a given design flow QvAnd lift H, pump casing radius RsRadius of pump shaft RZThe change of the three variables of the rotating speed n can bring the change of the outlet flow velocity of the moving blade of the coolant, so that the optimal solution of the three variables is solved under the condition that the sine value of the outlet angle of the moving blade is greater than 0, and the inflow velocity V of the coolant at the moving blade corresponding to the three parameters is enabled to be1And minimum. Pump casing radius R from solutionsRadius of pump shaft RZAnd the specific numerical values of the three variables of the rotating speed n can obtain all the design parameters of the pump under the design state.
Figure BDA0002668555260000071
Figure BDA0002668555260000072
t=Dnπ/Z
Figure BDA0002668555260000073
Figure BDA0002668555260000074
Figure BDA0002668555260000081
α3=α3∞+Δα
Figure BDA0002668555260000082
The optimal design scheme of the pump is obtained through the design, and the corrosion of the lead-based alloy lead-based coolant to the pump body and the energy loss of the lead-based alloy lead-based coolant are reduced. On the basis of the invention, the inlet and the outlet of the pump can be optimally designed. For example, the outlet of the pump is suggested to be designed in a gradually widening mode, under the condition that the flow and the lift requirements are met, the flow rate of the coolant is further reduced, and the corrosion of the lead-based alloy to the pump body is reduced.
While the invention has been described in further detail with reference to specific preferred embodiments thereof, it will be understood by those skilled in the art that various changes in form and details may be made therein without departing from the spirit and scope of the invention as defined by the appended claims.

Claims (4)

1. A hydraulic performance optimization design method of a lead-cooled fast reactor nuclear main pump is characterized by comprising the following steps: at the point of satisfying a given design flow QvAnd the pump shell radius R under the condition of the head HsRadius of pump shaft RZAnd the rotating speed n to obtain the optimal solution to determine the optimal design parameters of the pump and ensure the inlet flow velocity V of the coolant at the moving blade1And corresponding main pump inlet and outletThe port velocity is minimal; wherein the optimal combination of the three variables is determined by the following conditions: the arcsine function value of the liquid flow angle at the outlet of the moving blade is more than 0; radius of pump shaft RZSmaller than the radius of the hub, i.e. the radius R of the pump casings(ii) a Radius R of pump casingsRadius of pump shaft RzThe three parameter values of the rotating speed n are all larger than 0; radius R of pump casingsRadius of pump shaft RzThree parameter values of rotating speed n and inlet flow velocity V1The constraint relationship of (1) is as follows:
Figure FDA0002668555250000011
wherein: etav-the lead based pump volume factor is the ratio of the actual flow to the theoretical flow;
Figure FDA0002668555250000012
the blade displacement coefficient is the ratio of the actual flow cross-sectional area to the flow cross-sectional area of the flow channel without considering the blade thickness;
the design of the moving blades and the guide blades adopts a plane cascade theory, and the flow channel of the lead bismuth pump is divided into a plurality of coaxial cylindrical flow surfaces;
axial velocity v of moving blade corresponding to inlet on single cylindrical flow surfacem1And axial velocity v of the outletm2Is obtained by the following formula, wherein AflowThe cross-sectional flow area of the cylindrical flow passage in the pump,
Figure FDA0002668555250000021
radius R of pump casingsRadius of pump shaft RzAfter the rotating speed n is determined, the relative circumferential component speed u of the pump shaft side can be obtained, and the absolute velocity circumferential component v of the moving blade inlet is accelerated because the lead-based alloy of the moving blade inlet does not act on the moving bladeu1Neglecting the size, taking the value of 0, and considering the circumferential component v of the absolute velocity of the moving blade outlet in the practical optimization processu2And (3) performing linear correction:
Figure FDA0002668555250000022
in the formula: h-theoretical design head, vu2The absolute speed circumferential component of the outlet of the moving blade, xi is a correction coefficient, and the value is taken from the pump shaft to the pump shell according to the linearity: 0.9 to 1.1;
inlet flow angle beta of moving blades at corresponding cylindrical flow surface1And outlet flow angle beta2Determined by the following equation:
Figure FDA0002668555250000023
inlet angle alpha of guide vane3Determined by the following equation:
Figure FDA0002668555250000024
α3=α3∞+Δα
α3∞for theoretical inlet angle, Δ α guide vane inlet attack angle, guide vane function to eliminate velocity ringing at the moving vane outlet and reduce flow velocity of lead-based coolant, it is desirable that the lead-based coolant be able to flow out in the axial direction after exiting the guide vane, where guide vane outlet angle α4Directly taking 90 degrees;
the pitch between the moving blades is t, the number of the moving blades of the lead-based pump is Z, and
t=Dnπ/Z
Dn-the nth layer of cylindrical flow surface diameter;
length l of moving blade airfoil
Figure FDA0002668555250000031
K is a calculation proportionality coefficient;
the width W of the flow passage in the guide vane area is taken as the radius R of the pump shellsMinus pump shaft radius RzLength l of guide vane profilecDetermined by the following equation:
Figure FDA0002668555250000032
the wrap angle of the moving blade is 70-90 degrees, the setting angle of the guide blade outlet is 90 degrees, the thickness of the impeller blade is 5-7mm, and the thickness of the guide blade is 4-6 mm.
2. The hydraulic performance optimization design method of the lead-cooled fast reactor nuclear main pump according to claim 1, characterized in that: lead-based pump volume coefficient etavTake 0.95.
3. The hydraulic performance optimization design method of the lead-cooled fast reactor nuclear main pump according to claim 1, characterized in that: the incidence angle delta alpha of the guide vane inlet is 0-4 degrees.
4. The hydraulic performance optimization design method of the lead-cooled fast reactor nuclear main pump according to claim 1, characterized in that: and calculating the value of the proportionality coefficient K to be 1.3-1.4.
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