A heat exchange system based on nuclear energy utilization

Abstract

The utility model belongs to nuclear reactor heat exchange system technical field. Provide a kind of heat exchange system based on nuclear energy utilization, including: nuclear reactor two loop high temperature high pressure water subsystem, three loop desalted water subsystem and multiple sets of heat exchanger group, each set of heat exchanger group includes one preheater, one kettle type evaporator and one superheater;The utility model belongs to three loop system design, by reactor one loop, intermediate isolation two loop, steam generating system three loop composition, for the three loop system of steam supply user one loop medium heat exchange, but through the heat exchange of intermediate isolated two loop and produce steam, isolate the radioactive propagation to user side, reduce the risk of radioactive material leakage, improve safety.

Description

TECHNICAL FIELD

[0001] The utility model relates to nuclear reactor heat exchange system technical field, especially a heat exchange system based on nuclear energy utilization. BACKGROUND

[0002] The statements in this section merely provide background information related to the utility model and do not necessarily constitute the prior art.

[0003] Nuclear energy as clean energy has the advantages of high energy density, mature existing technology and great development potential, can supplement or even replace fossil fuels in the application of heating, industry and power generation, and reduce carbon emissions and pollutant emissions, wherein the design of nuclear energy heat exchange system is an important link to realize nuclear energy utilization.

[0004] The current nuclear reactor heat exchange system has a double loop heat exchange system design, the double loop heat exchange system is composed of a loop system driven by the heat of the reactor core and a two loop system which exchanges heat with the one loop system through a heat exchanger, the one loop medium directly contacts the reactor core, the heat is transmitted to the two loop through the heat exchanger, and the two loop directly generates steam to supply to the user, if the heat exchanger has a leakage, the risk of radioactive substances in the steam supplied to the user will greatly increase, and moreover, the existing heat exchange system designs a single heat exchanger group according to full load condition, without considering the operation of the system under other load conditions, without leaving redundancy, and the variable load operation capacity is poor.

[0005] The existing steam drum type evaporator design scheme (i.e. multiple evaporators share a steam drum) produces a mixture of saturated water and saturated steam, the saturated water enters the evaporator through the downcomer, and the saturated steam enters the superheater through the riser, the design of multiple evaporators sharing a steam drum is complex, the evaporator is arranged asymmetrically, and the water power field and temperature field are easily unbalanced due to the change of working condition, and the equipment operation has risks, and the steam drum and the evaporator are operated as a whole, if one evaporator leaks, the whole needs to be shut down for maintenance, and the isolated operation of a single evaporator cannot be realized. UTILITY MODEL CONTENTS

[0006] In order to solve the problems of the prior art, the utility model provides a heat exchange system based on nuclear energy utilization, which belongs to a three loop system design, is composed of a reactor one loop, an intermediate isolation two loop and a steam generating system three loop, the three loop system for supplying steam to the user does not exchange heat with the one loop medium, but exchanges heat through the intermediate isolation two loop to generate steam, the radioactive propagation to the user side is isolated, the risk of radioactive material leakage is reduced, and the safety is improved.

[0007] In order to realize the above purpose, the utility model adopts the following technical scheme:

[0008] A heat exchange system based on nuclear energy utilization, comprising: a nuclear reactor secondary loop high-temperature high-pressure water subsystem, a tertiary loop desalted water subsystem and a plurality of heat exchanger groups, each heat exchanger group comprising a preheater, a kettle-type evaporator and a superheater;

[0009] In the nuclear reactor secondary loop high-temperature high-pressure water subsystem, a nuclear reactor secondary loop water inlet is connected with the tube side inlet of each superheater in the plurality of heat exchanger groups through a secondary loop water inlet main line A, a secondary loop water inlet adjusting valve group is arranged on the secondary loop water inlet main line, the tube side outlet of the superheater is connected with the tube side inlet of the corresponding kettle-type evaporator, the tube side outlet of the kettle-type evaporator is connected with the tube side inlet of the corresponding preheater, and a nuclear reactor secondary loop water outlet is connected with the tube side outlet of each preheater in the plurality of heat exchanger groups through a secondary loop water outlet main line.

[0010] In the tertiary loop desalted water subsystem, a tertiary loop water supply inlet is connected with the shell side inlet of each preheater in the plurality of heat exchangers through a desalted water supply main line, a desalted water supply pump group is arranged at one end of the desalted water supply main line close to the tertiary loop water supply inlet, a first inlet of a deaerator is connected with the shell side outlet of each preheater in the plurality of heat exchangers through a deaerator inlet main line, and an outlet of the deaerator is connected with the shell side inlet of each kettle-type evaporator in the plurality of heat exchangers through a kettle-type evaporator shell side inlet main line.

[0011] A feed water pump group and a feed water adjusting valve group are arranged at one end of the kettle-type evaporator shell side inlet main line close to the deaerator, the shell side outlet of each kettle-type evaporator in the plurality of heat exchangers is connected with the shell side inlet of each superheater through a plurality of saturated steam pipelines, a second inlet of the deaerator is connected with the shell side outlet of each superheater through a superheated steam outlet main line, and a superheater outlet adjusting valve group is arranged at one end of the superheated steam outlet main line close to the deaerator.

[0012] As a further limitation of the utility model, the nuclear reactor secondary loop high-temperature high-pressure water subsystem further comprises: a superheater tube side water inlet adjusting valve group, a superheater tube side water outlet adjusting valve group, a preheater tube side water inlet adjusting valve group and a preheater tube side water outlet adjusting valve group, the tube side inlet of each superheater is connected with the secondary loop water inlet main line through a superheater tube side inlet branch line, and the superheater tube side inlet branch line is provided with the superheater tube side water inlet adjusting valve group.

[0013] The tube side outlet of each superheater is connected with the tube side inlet of the kettle-type evaporator through a superheater tube side outlet branch line, and the superheater tube side outlet branch line is provided with the superheater tube side water outlet adjusting valve group.

[0014] The tube side inlet of each preheater is connected with the tube side outlet of the kettle-type evaporator through a preheater tube side inlet branch line, and the preheater tube side inlet branch line is provided with the preheater tube side water inlet adjusting valve group.

[0015] The tube side outlet of each preheater is connected with the main water supply line of the secondary circuit through a preheater tube side outlet branch, and a preheater tube side water regulating valve group is arranged on the preheater tube side outlet branch.

[0016] As a further limitation of the utility model, the three-circuit desalted water subsystem further comprises a preheater shell side inlet water regulating valve group, a deaerator inlet water regulating valve group, a kettle-type evaporator inlet water regulating valve group, a saturated steam regulating valve group and a superheated steam regulating valve group.

[0017] The shell side inlet of each preheater is connected with the desalted water supply main line through a preheater shell side inlet branch, and a preheater shell side inlet water regulating valve group is arranged on the preheater shell side inlet branch.

[0018] The shell side outlet of each preheater is connected with the deaerator inlet main line through a deaerator inlet branch, and a deaerator inlet water regulating valve group is arranged on the deaerator inlet branch.

[0019] The shell side inlet of each kettle-type evaporator is connected with the kettle-type evaporator inlet main line through a kettle-type evaporator inlet branch, and a kettle-type evaporator inlet water regulating valve group is arranged on the kettle-type evaporator inlet branch.

[0020] The shell side outlet of each kettle-type evaporator is connected with the shell side inlet of the superheater through a saturated steam pipeline, and a saturated steam regulating valve group is arranged on the saturated steam pipeline.

[0021] The shell side outlet of each superheater is connected with the superheated steam outlet main line through a superheated steam branch, and a superheated steam regulating valve group is arranged on the superheated steam branch.

[0022] As a further limitation of the utility model, the three-circuit desalted water subsystem further comprises a desalted water tank, a desalted water regulating valve group and a desalted water pipeline, and the desalted water supply main line is provided with the desalted water tank near one end of the three-circuit make-up water inlet, and the desalted water pipeline is connected with the three-circuit make-up water inlet and the inlet of the desalted water make-up pump group respectively.

[0023] As a further limitation of the utility model, the three-circuit desalted water subsystem further comprises a desalted water control valve group, a water supply bypass and a water supply bypass regulating valve group, and the desalted water supply main line is provided with the desalted water control valve group near one end of the desalted water make-up pump group.

[0024] One end of the water supply bypass is connected with the outlet of the desalted water control valve group, and the other end of the water supply bypass is connected with the third inlet of the deaerator, and the water supply bypass is provided with the water supply bypass regulating valve group.

[0025] As a further limitation of the utility model, the three loop desalted water subsystem further comprises: a recirculation pump, a recirculation water main line and a plurality of recirculation water branches, one end of the recirculation water main line is connected with the fourth inlet of the deaerator, the other end of the recirculation water main line is connected with one end of the plurality of recirculation water branches respectively.

[0026] The one end of the recirculation water main line close to the deaerator is provided with the recirculation pump, the bottom of each kettle type evaporator is provided with a liquid water outlet, and the other end of the plurality of recirculation water branches is connected with the liquid water outlet of the plurality of kettle type evaporators respectively.

[0027] As a further limitation of the utility model, the three loop desalted water subsystem further comprises: a recirculation pump, a recirculation water main line and a plurality of recirculation water branches, one end of the recirculation water main line is connected with the fourth inlet of the deaerator, the other end of the recirculation water main line is connected with one end of the plurality of recirculation water branches respectively.

[0028] As a further limitation of the utility model, the three loop desalted water subsystem further comprises: a recirculation pump, a recirculation water main line and a plurality of recirculation water branches, one end of the recirculation water main line is connected with the fourth inlet of the deaerator, the other end of the recirculation water main line is connected with one end of the plurality of recirculation water branches respectively.

[0029] As a further limitation of the utility model, the three loop desalted water subsystem further comprises: a recirculation pump, a recirculation water main line and a plurality of recirculation water branches, one end of the recirculation water main line is connected with the fourth inlet of the deaerator, the other end of the recirculation water main line is connected with one end of the plurality of recirculation water branches respectively.

[0030] The desalted water supplement pump group comprises two desalted water supplement pumps and two desalted water pipelines, one end of the two desalted water pipelines is connected with the outlet of the desalted water regulating valve group, the other end of the two desalted water pipelines is connected with the inlet of the desalted water control valve group, and the two desalted water pipelines are respectively provided with the two desalted water supplement pumps.

[0031] As a further limitation of the utility model, the three loop desalted water subsystem further comprises: a recirculation pump, a recirculation water main line and a plurality of recirculation water branches, one end of the recirculation water main line is connected with the fourth inlet of the deaerator, the other end of the recirculation water main line is connected with one end of the plurality of recirculation water branches respectively.

[0032] Compared with the prior art, the utility model has the beneficial effects that:

[0033] 1. The heat exchange system can realize heat exchange between high-temperature and high-pressure water of a nuclear reactor secondary loop and desalted water of a nuclear reactor tertiary loop, the nuclear reactor secondary loop serves as an intermediate isolation loop and only brings nuclear reactor heat, the contact between the tertiary loop steam and the nuclear reactor is isolated, the radiation leakage risk is reduced, and the steam safety is high.

[0034] 2. The heat exchange system is provided with three sets of heat exchanger groups arranged side by side, each set of heat exchanger group is designed according to 50% of the maximum load capacity, and each set of heat exchanger group runs or is cut off without interference. Three sets of heat exchanger groups can be put into use in normal operation, once a set of heat exchanger group fails, the set of heat exchanger group can be cut off through the adjusting valve group, and the remaining two sets of heat exchanger groups run side by side, and each set of heat exchanger group bears 1 / 2 load; the heat exchange system is effectively improved in risk resistance, the heat exchange system can normally work under the condition of heat exchanger failure, nuclear reactor heat is timely taken away, and the safe operation of the overall system is ensured.

[0035] 3. The adjusting valve group is arranged at the pipeline at the inlet and outlet of the heat exchanger in the heat exchange system, the inlet side and / or the outlet side of each branch pipeline, the valve group is used for controlling the pipeline resistance of each group of heat exchanger branches, so that the flow distribution between the running heat exchanger groups is achieved. The flow distribution between the heat exchanger groups can be controlled, and the parallel operation of the heat exchanger groups is realized.

[0036] 4. The heat exchange system is provided with a feedwater bypass before the preheater, part of the desalted water can directly enter the deaerator without passing through the preheater, which is helpful for controlling the medium outlet temperature, the medium temperature in the preheater and the deaerator, and the secondary loop return water temperature.

[0037] 5. The heat exchange system is further connected with a condenser and an emptying atmosphere pipeline at the outlet of the superheater, in special cases (start-up, shutdown and accidents), steam cannot be utilized, the steam can be discharged or condensed and recovered, nuclear reactor heat is timely taken away, and the safe and stable operation of the overall system is ensured.

[0038] 6. The heat exchange system is provided with a desalted water tank at the inlet of the tertiary loop, which serves as a supplement of the tertiary loop feed water. When the desalted water supply is insufficient, the desalted water tank can supply the tertiary loop feed water, so that the heat exchange system can stably run for a period of time and the risk resistance of the system is improved.

[0039] 7. The heat exchange system is provided with a superheater outlet adjusting valve group at the outlet of the superheater, the flow distribution of the superheated steam can be controlled, the steam can be used for heating feed water of the deaerator, heating and supplying industrial production, and the nuclear energy steam is fully utilized.

[0040] The advantages of the additional aspects of the utility model will be partially given in the following description, some will become apparent from the following description, or be understood through the practice of the utility model. Attached Figure Description

[0041] The accompanying drawings, which form part of this specification, are used to provide a further understanding of this utility model. The illustrative embodiments of this utility model and their descriptions are used to explain this utility model and do not constitute an improper limitation of this utility model.

[0042] Figure 1 This is a schematic diagram of the structure of the heat exchange system based on nuclear energy utilization provided by this utility model;

[0043] In the diagram: 1. Secondary loop return water inlet; 2. Preheater; 3. Evaporator; 4. Superheater; 5. Secondary loop inlet; 6. Secondary loop inlet regulating valve assembly; 7. Recirculation pump; 8. Superheater outlet regulating valve assembly; 9. Deaerator; 10. Heating supply pipeline; 11. Industrial steam supply pipeline; 12. Seawater desalination supply pipeline; 13. Vent to atmospheric air pipeline; 14. Condenser; 15. Feedwater pump assembly; 16. Feedwater regulating valve assembly; 17. Tertiary loop makeup water inlet; 18. Demineralized water tank; 19. Demineralized water regulating valve assembly; 20. Demineralized water makeup water pump assembly; 21. Demineralized water control valve assembly; 22. Feedwater bypass regulating valve assembly; 23. Secondary loop regulating valve assembly; A. Secondary loop main inlet line; B. Secondary loop main return line; C. Demineralized water feedwater main line; D. Deaerator inlet main line; E. Evaporator shell-side inlet main line; F. Superheated steam outlet main line; G. Demineralized water pipeline; H. Feedwater bypass; I. Recirculating water main line; J. Recirculating water branch line; K. Condensate recovery pipeline; L. Secondary loop bypass. Detailed Implementation

[0044] The present invention will be further described below with reference to the accompanying drawings and embodiments.

[0045] It should be noted that the following detailed description is exemplary and intended to provide further explanation of the present invention. Unless otherwise specified, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this invention pertains.

[0046] In this implementation, such as Figure 1 As shown, a heat exchange system based on nuclear energy utilization is proposed, which includes a high-temperature and high-pressure water subsystem of the secondary loop of the nuclear reactor, a demineralized water subsystem of the tertiary loop, and multiple heat exchanger sets. Each heat exchanger set includes a preheater 2, a kettle evaporator 3, and a superheater 4.

[0047] In the present embodiment, preferably, the nuclear reactor secondary loop high-temperature high-pressure water subsystem comprises a nuclear reactor secondary loop water inlet 5, a secondary loop water inlet regulating valve group 6, a nuclear reactor secondary loop water outlet 1, a secondary loop water inlet main line A and a secondary loop water outlet main line B, the nuclear reactor secondary loop water inlet 5 is connected to the tube side inlet of each superheater 4 in the plurality of heat exchanger groups through the secondary loop water inlet main line A, the secondary loop water inlet main line A is provided with the secondary loop water inlet regulating valve group 6, the tube side outlet of the superheater 4 is connected to the tube side inlet of the corresponding kettle-type evaporator 3, the tube side outlet of the kettle-type evaporator 3 is connected to the tube side inlet of the corresponding preheater 2, and the nuclear reactor secondary loop water outlet 1 is connected to the tube side outlet of each preheater 2 in the plurality of heat exchanger groups through the secondary loop water outlet main line B.

[0048] In the present embodiment, preferably, the three-loop desalted water subsystem comprises a three-loop makeup water inlet 17, a desalted water makeup water pump group 20, a deaerator 9, a desalted water feed water main line C, a deaerator inlet main line D, a kettle-type evaporator shell side inlet main line E, a feed water pump group 15, a feed water regulating valve group 16, a superheated steam outlet main line F and a superheater outlet regulating valve group 8, the three-loop makeup water inlet 17 is connected to the shell side inlet of each preheater 2 in the plurality of heat exchangers through the desalted water feed water main line C, the desalted water feed water main line C is provided with the desalted water makeup water pump group 20 at the end close to the three-loop makeup water inlet 17, the first inlet of the deaerator 9 is connected to the shell side outlet of each preheater 2 in the plurality of heat exchangers through the deaerator inlet main line D, the outlet of the deaerator 9 is connected to the shell side inlet of each kettle-type evaporator in the plurality of heat exchangers through the kettle-type evaporator shell side inlet main line E, the kettle-type evaporator shell side inlet main line E is provided with the feed water pump group 15 and the feed water regulating valve group 16 at the end close to the deaerator 9, the shell side outlet of each kettle-type evaporator 3 in the plurality of heat exchangers is connected to the shell side inlet of each superheater 4 through a plurality of saturated steam pipelines, the second inlet of the deaerator 9 is connected to the shell side outlet of each superheater 4 through the superheated steam outlet main line F, and the superheated steam outlet main line F is provided with the superheater outlet regulating valve group 8 at the end close to the deaerator 9.

[0049] In the present embodiment, preferably, the nuclear reactor secondary loop high-temperature high-pressure water subsystem further comprises a superheater tube side water inlet regulating valve group, a superheater tube side water outlet regulating valve group, a preheater tube side water inlet regulating valve group and a preheater tube side water outlet regulating valve group, the tube side inlet of each superheater 4 is connected to the secondary loop water inlet main line A through a superheater tube side inlet branch, and the superheater tube side inlet branch is provided with the superheater tube side water inlet regulating valve group;

[0050] the tube side outlet of each superheater 4 is connected to the tube side inlet of the kettle-type evaporator 3 through a superheater tube side outlet branch, and the superheater tube side outlet branch is provided with the superheater tube side water outlet regulating valve group;

[0051] The tube side inlet of each preheater 2 is connected with the tube side outlet of the kettle evaporator 3 through a preheater tube side inlet branch, and a preheater tube side inlet water regulating valve group is arranged on the preheater tube side inlet branch;

[0052] The tube side outlet of each preheater 2 is connected with the two-loop backwater main road B through a preheater tube side outlet branch, and a preheater tube side outlet water regulating valve group is arranged on the preheater tube side outlet branch.

[0053] In the present embodiment, preferably, the three-loop desalted water subsystem further comprises a preheater shell side inlet water regulating valve group, a deaerator inlet water regulating valve group, a kettle evaporator inlet water regulating valve group, a saturated steam regulating valve group and a superheated steam regulating valve group, the shell side inlet of each preheater 2 is connected with the desalted water feed water main road C through a preheater shell side inlet branch, and a preheater shell side inlet water regulating valve group is arranged on the preheater shell side inlet branch;

[0054] The shell side outlet of each preheater 2 is connected with the deaerator inlet main road D through a deaerator inlet branch, and a deaerator inlet water regulating valve group is arranged on the deaerator inlet branch;

[0055] The shell side inlet of each kettle evaporator 3 is connected with the kettle evaporator inlet main road through a kettle evaporator inlet branch, and a kettle evaporator inlet water regulating valve group is arranged on the kettle evaporator inlet branch;

[0056] The shell side outlet of each kettle evaporator 3 is connected with the shell side inlet of the superheater 4 through a saturated steam pipeline, and a saturated steam regulating valve group is arranged on the saturated steam pipeline;

[0057] The shell side outlet of each superheater 4 is connected with the superheated steam outlet main road F through a superheated steam branch, and a superheated steam regulating valve group is arranged on the superheated steam branch.

[0058] In the present embodiment, preferably, the three-loop desalted water subsystem further comprises a desalted water tank 18, a desalted water regulating valve group 19 and a desalted water pipeline G, the desalted water feed water main road C is provided with the desalted water tank 18 near one end of the three-loop make-up water port 17, and the desalted water pipeline G is connected with the three-loop make-up water port 17 and the inlet of the desalted water make-up pump group 20 respectively.

[0059] In the present embodiment, preferably, the three-loop desalted water subsystem further comprises a desalted water control valve group 21, a feed water bypass H and a feed water bypass regulating valve group 22, the desalted water feed water main road C is provided with the desalted water control valve group 21 near one end of the desalted water make-up pump group 20, one end of the feed water bypass H is connected with the outlet of the desalted water control valve group 21, the other end of the feed water bypass H is connected with the third inlet of the deaerator 9, and the feed water bypass H is provided with the feed water bypass regulating valve group 22.

[0060] In the present embodiment, preferably, the three-loop desalted water subsystem further comprises a recirculation pump 7, a recirculation water main line I and a plurality of recirculation water branch lines J, one end of the recirculation water main line I is connected with the fourth inlet of the deaerator 9, the other end of the recirculation water main line I is respectively connected with one end of the plurality of recirculation water branch lines J, the recirculation water main line I is provided with the recirculation pump 7 at the end close to the deaerator 9, each kettle-type evaporator 3 is provided with a liquid water outlet at the bottom, the other end of the plurality of recirculation water branch lines J is respectively connected with the liquid water outlet of the plurality of kettle-type evaporators 3.

[0061] In the present embodiment, preferably, the three-loop desalted water subsystem further comprises a heating supply line 10, an industrial steam supply line 11 and a seawater desalination supply line 12, the heating supply line 10, the industrial steam supply line 11 and the seawater desalination supply line 12 are respectively connected with the outlet of the superheater outlet regulating valve group 8 through three supply branch lines.

[0062] In the present embodiment, preferably, the three-loop desalted water subsystem further comprises an external air exhaust line 13, a condenser 14 and a condensate water recovery line K, the inlet of the external air exhaust line 13 and the condenser 14 are respectively connected with the outlet of the superheater outlet regulating valve group 8 through two supply branch lines, the outlet of the condenser 14 is connected with the desalted water tank 18 through the condensate water recovery line K.

[0063] In the present embodiment, preferably, the feedwater pump group 15 comprises two feedwater pumps and two feedwater lines, one end of the two feedwater lines is connected with the outlet of the deaerator 9, the other end of the two feedwater lines is connected with the inlet of the feedwater regulating valve group 16, the two feedwater lines are respectively provided with the two feedwater pumps.

[0064] The desalted water makeup pump group 20 comprises two desalted water makeup pumps and two desalted water lines, one end of the two desalted water lines is connected with the outlet of the desalted water regulating valve group 19, the other end of the two desalted water lines is connected with the inlet of the desalted water control valve group 21, the two desalted water lines are respectively provided with the two desalted water makeup pumps.

[0065] In the present embodiment, preferably, the nuclear reactor two-loop high-temperature and high-pressure water subsystem further comprises a two-loop regulating valve group 23 and a two-loop bypass line L, one end of the two-loop bypass line L is connected with the outlet of the two-loop inlet water regulating valve group 6, the other end of the two-loop bypass line L is connected with the nuclear reactor two-loop water outlet 1, the two-loop bypass line L is provided with the two-loop regulating valve group 23.

[0066] The above merely describes the preferred embodiments of the present application and is not intended to limit the present application. For those skilled in the art, the present application can be variously changed and modified. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present application shall be included in the protection scope of the present application.

Claims

1. A heat exchange system based on nuclear energy utilization, characterized by, include: The nuclear reactor has a secondary loop high-temperature and high-pressure water subsystem, a tertiary loop demineralized water subsystem, and multiple heat exchanger sets. Each heat exchanger set includes a preheater, a batch evaporator, and a superheater. In the high-temperature and high-pressure water subsystem of the nuclear reactor secondary loop, the nuclear reactor secondary loop inlet is connected to the tube-side inlet of each superheater in multiple heat exchanger groups through the secondary loop main inlet A. The secondary loop main inlet is equipped with a secondary loop inlet regulating valve group. The tube-side outlet of the superheater is connected to the tube-side inlet of the corresponding autoclave evaporator. The tube-side outlet of the autoclave evaporator is connected to the tube-side inlet of the corresponding preheater. The nuclear reactor secondary loop return outlet is connected to the tube-side outlet of each preheater in multiple heat exchanger groups through the secondary loop return water main. In the three-loop demineralized water subsystem, the three-loop makeup water inlets are connected to the shell-side inlets of each preheater in the multiple heat exchangers via the demineralized water supply main line. A demineralized water makeup water pump group is provided at the end of the demineralized water supply main line near the three-loop makeup water inlets. The first inlet of the deaerator is connected to the shell-side outlet of each preheater in the multiple heat exchangers via the deaerator inlet main line. The outlet of the deaerator is connected to the shell-side inlet of each autoclave in the multiple heat exchangers via the autoclave shell-side inlet main line. The main inlet of the reactor evaporator shell side is equipped with a feedwater pump group and a feedwater regulating valve group at the end near the deaerator. The shell side outlet of each reactor evaporator in the multiple heat exchangers is connected to the shell side inlet of each superheater through multiple saturated steam pipelines. The second inlet of the deaerator is connected to the shell side outlet of each superheater through the main superheated steam outlet. The superheated steam outlet main line is equipped with a superheater outlet regulating valve group at the end near the deaerator.

2. The heat exchange system based on nuclear energy utilization as described in claim 1, characterized in that, The high-temperature and high-pressure water subsystem of the nuclear reactor secondary loop also includes: a superheater tube-side inlet water regulating valve group, a superheater tube-side outlet water regulating valve group, a preheater tube-side inlet water regulating valve group, and a preheater tube-side outlet water regulating valve group. The tube-side inlet of each superheater is connected to the secondary loop main water inlet through a superheater tube-side inlet branch. A superheater tube-side inlet water regulating valve group is provided on the superheater tube-side inlet branch. Each superheater's tube-side outlet is connected to the tube-side inlet of the autoclave evaporator via a superheater tube-side outlet branch, and a superheater tube-side outlet regulating valve group is provided on the superheater tube-side outlet branch. Each preheater's tube-side inlet is connected to the tube-side outlet of the autoclave evaporator via a preheater tube-side inlet branch, and a preheater tube-side water inlet regulating valve group is provided on the preheater tube-side inlet branch. Each preheater's pipe-side outlet is connected to the secondary return water main line via a preheater pipe-side outlet branch, and a preheater pipe-side outlet regulating valve group is provided on the preheater pipe-side outlet branch.

3. The heat exchange system based on nuclear energy utilization as described in claim 1, characterized in that, The three-loop demineralized water subsystem further includes: a preheater shell-side water inlet regulating valve group, a deaerator water inlet regulating valve group, a kettle evaporator water inlet regulating valve group, a saturated steam regulating valve group, and a superheated steam regulating valve group; The shell side inlet of each preheater is connected with the main line of the desalted water supply through a preheater shell side inlet branch line, and a preheater shell side water inlet adjusting valve group is arranged on the preheater shell side inlet branch line; The shell side outlet of each preheater is connected with the main line of the deaerator inlet through a deaerator inlet branch line, and a deaerator water inlet adjusting valve group is arranged on the deaerator inlet branch line; The shell side inlet of each kettle evaporator is connected with the main line of the kettle evaporator inlet through a kettle evaporator inlet branch line, and a kettle evaporator water inlet adjusting valve group is arranged on the kettle evaporator inlet branch line; The shell side outlet of each kettle evaporator is connected with the shell side inlet of the superheater through a saturated steam pipeline, and a saturated steam adjusting valve group is arranged on the saturated steam pipeline; The shell side outlet of each superheater is connected with the main line of the superheated steam outlet through a superheated steam branch line, and a superheated steam adjusting valve group is arranged on the superheated steam branch line.

4. The heat exchange system based on nuclear energy utilization according to claim 1, wherein the three-loop desalted water subsystem further comprises a desalted water tank, a desalted water adjusting valve group and a desalted water pipeline, and the main line of the desalted water supply is provided with the desalted water tank near one end of the three-loop makeup water port, and the desalted water pipeline is connected with the three-loop makeup water port and the inlet of the desalted water makeup pump group respectively.

5. The heat exchange system based on nuclear energy utilization according to claim 1, wherein the three-loop desalted water subsystem further comprises a desalted water control valve group, a water supply bypass and a water supply bypass adjusting valve group, and the main line of the desalted water supply is provided with the desalted water control valve group near one end of the desalted water makeup pump group; one end of the water supply bypass is connected with the outlet of the desalted water control valve group, the other end of the water supply bypass is connected with the third inlet of the deaerator, and the water supply bypass is provided with the water supply bypass adjusting valve group.

6. The heat exchange system based on nuclear energy utilization according to claim 1, wherein the three-loop desalted water subsystem further comprises a recirculation pump, a recirculation water main line and a plurality of recirculation water branch lines, one end of the recirculation water main line is connected with the fourth inlet of the deaerator, the other end of the recirculation water main line is connected with one end of the plurality of recirculation water branch lines respectively; the recirculation pump is arranged near one end of the recirculation water main line close to the deaerator, each kettle evaporator is provided with a liquid water outlet at the bottom, and the other end of the plurality of recirculation water branch lines is connected with the liquid water outlet of the plurality of kettle evaporators respectively.

7. The heat exchange system based on nuclear energy utilization according to claim 1, wherein the three-loop desalted water subsystem further comprises a heating supply pipeline, an industrial steam supply pipeline and a seawater desalination supply pipeline, and the heating supply pipeline, the industrial steam supply pipeline and the seawater desalination supply pipeline are connected with the outlet of the superheater outlet adjusting valve group through three supply branch lines respectively.

8. The heat exchange system based on nuclear energy utilization according to claim 1, wherein the three-loop desalted water subsystem further comprises an external air exhaust pipeline, a condenser and a condensate recovery pipeline, the external air exhaust pipeline and the inlet of the condenser are connected with the outlet of the superheater outlet adjusting valve group through two supply branch lines respectively, and the outlet of the condenser is connected with the desalted water tank through the condensate recovery pipeline. ​ ​ ​ ​ ​ 9. The nuclear energy utilization based heat exchange system according to claim 1, wherein the feedwater pump set comprises two feedwater pumps and two feedwater pipes, one end of the two feedwater pipes is connected with the outlet of the deaerator, the other end of the two feedwater pipes is connected with the inlet of the feedwater regulating valve set, and the two feedwater pipes are respectively provided with the two feedwater pumps; the desalted water supplement pump set comprises two desalted water supplement pumps and two desalted water pipes, one end of the two desalted water pipes is connected with the outlet of the desalted water regulating valve set, the other end of the two desalted water pipes is connected with the inlet of the desalted water control valve set, and the two desalted water pipes are respectively provided with the two desalted water supplement pumps.

10. The nuclear energy utilization based heat exchange system according to claim 1, wherein the high temperature and high pressure water sub-system of the nuclear reactor secondary loop further comprises a secondary loop regulating valve set and a secondary loop bypass, one end of the secondary loop bypass is connected with the outlet of the secondary loop water inlet regulating valve set, the other end of the secondary loop bypass is connected with the nuclear reactor secondary loop water outlet, and the secondary loop bypass is provided with the secondary loop regulating valve set. ​ ​

Images