Radiation waste boiler and gasifier containing same, heat recovery system and heat recovery process

Abstract

The present invention discloses a radiation waste boiler and a gasifier, a heat recovery system and a heat recovery process containing the same. The radiation waste boiler comprises: a cylindrical water-cooled wall, the cylindrical water-cooled wall is arranged along the inner wall surface of the radiation waste boiler circumferentially to form a circumferentially sealed radiation waste boiler cavity; multiple groups of heat exchange units, the multiple groups of heat exchange units are arranged in the radiation waste boiler cavity and distributed circumferentially; each group of heat exchange units includes a convection section and a first radiation screen, the convection section and the first radiation screen are on the same straight line, and are arranged in sequence along the central axis direction from the cylindrical water-cooled wall to the radiation waste boiler cavity; the first radiation screen and the convection section of each group of heat exchange units form a long radiation screen; the width of the first radiation screen is greater than the width of the convection section; the width refers to the maximum circumferential dimension. The radiation waste boiler provided by the present invention can generate superheated steam, and the water-cooled pipe of the superheated steam is not easy to dry burn, while reducing the height of the radiation waste boiler and reducing the investment cost.

Description

Technical Field

[0001] The invention relates to a radiation waste cooker and a gasification furnace containing the same, a heat recovery system and a heat recovery process. Background Art

[0002] The coal gasification process is a process that uses oxygen (air, oxygen-enriched or industrial pure oxygen) and water vapor as gasifying agents to convert the combustible part of coal or coal coke into synthesis gas / combustible gas through chemical reactions. Entrained-bed gasification technology has become the mainstream technology for coal gasification today due to its good technical indicators, high processing load and environmental friendliness. The entrained-bed gasification process is characterized by high temperature, that is, pure oxygen / oxidant is used to partially oxidize coal, so that most of the combustibles in the coal are converted into synthesis gas / combustible gas at a high temperature of 1300°C. At such a high temperature, the high-temperature synthesis gas / combustible gas out of the gasifier contains a large amount of high-grade sensible heat. With the increasing requirements for energy utilization in the coal conversion process, how to effectively recover the heat from the high-temperature synthesis gas out of the gasification chamber has become an increasingly urgent problem that needs to be solved.

[0003] In order to recover the sensible heat of high-temperature synthesis gas, corresponding radiation boilers have been developed, such as GE water-coal slurry gasification radiation waste boiler, multi-nozzle water-coal slurry gasification radiation waste boiler, Jinhua furnace water-coal slurry gasification radiation waste boiler and other technologies, and all of them have achieved industrial operation. Chinese patent documents CN201110083947.X, CN 201310322452.7, CN201320708028, 201520077861.X, CN201810001028.5 disclose methods or equipment for recovering sensible heat from high-temperature synthesis gas by radiation heat transfer. The above prior art realizes the cooling of high-temperature synthesis gas and produces saturated steam of a certain pressure level as a by-product. However, it increases the radiation heat transfer area by adding a radiation screen or increasing the height of the radiation waste boiler to achieve effective recovery of the heat of the high-temperature synthesis gas, so there are limitations of high investment and no by-product of superheated steam. Chinese patent document CN108410510A discloses a waste boiler ash removal integrated coal gasification furnace, which divides the water-cooled wall into two sections, the lower section is the evaporation section, which produces saturated steam, and the upper section is the superheating section, which produces superheated steam. Although it solves the limitation of not being able to produce superheated steam as a by-product, its superheating section is directly exposed to the high heat flux density of high-temperature synthesis gas, and the temperature difference between the two sides of its pipeline is large, which is easy to cause dry burning and damage. In addition, the superheating section and the evaporation section are arranged up and down, so that an inlet and outlet pipeline must be provided in the middle of the boiler, which has the disadvantages of complex design and poor reliability. Summary of the invention

[0004] The technical problem to be solved by the present invention is to overcome the defects of the prior art that it cannot produce superheated steam as a by-product and has a high investment cost, and to provide a radiation waste boiler with low cost and the ability to produce superheated steam as a by-product, and a gasification furnace, a heat recovery system and a heat recovery process containing the same. The radiation waste boiler provided by the present invention can produce superheated steam as a by-product, and under the same processing capacity, the height of the radiation waste boiler of the present invention is greatly reduced compared with the prior art.

[0005] The present invention solves the above technical problems through the following technical solutions:

[0006] The present invention provides a radiation waste pot, which comprises:

[0007] A cylindrical water-cooled wall, wherein the cylindrical water-cooled wall is arranged circumferentially along the inner wall surface of the radiation waste boiler to form a circumferentially sealed radiation waste boiler cavity;

[0008] A plurality of heat exchange units, wherein the plurality of heat exchange units are arranged in the radiation waste pot cavity and distributed along the circumferential direction;

[0009] Each group of the heat exchange units comprises a convection section and a first radiation screen, wherein the convection section and the first radiation screen are located on the same straight line and are arranged in sequence along the central axis direction from the water-cooled wall of the cylinder to the cavity of the radiation waste boiler;

[0010] The first radiation screen and the convection section of each group of the heat exchange units form a long radiation screen;

[0011] The width of the first radiation screen is greater than the width of the convection section;

[0012] The width refers to the maximum dimension in the circumferential direction.

[0013] In the present invention, the cylindrical water-cooled wall may adopt a conventional radiation heat exchanger in the art, such as a radiation surface type or a radiation tube type, preferably a radiation tube type.

[0014] Wherein, the radiation tube type can be formed by connecting multiple radiation tubes through connecting ribs.

[0015] In the present invention, the lengths of the plurality of groups of long radiation screens may be the same or different, preferably the same.

[0016] The length refers to the dimension along the radial direction.

[0017] In the present invention, the convection section may adopt a conventional heat exchanger in the art, such as a shell-and-tube type or a coil type, preferably a shell-and-tube type.

[0018] In the present invention, the first radiation screen may adopt a conventional heat exchanger in the art, such as a shell-and-tube type or a coil type, preferably a shell-and-tube type.

[0019] In the present invention, the ratio of the width W1 of the first radiation screen to the width W2 of the convection section may be 3-7, preferably 4.

[0020] The width ratio of the first radiation screen and the convection section can affect the heat flux density of the convection section. A suitable width ratio can prevent the heat exchange tubes of the convection section from dry burning, while also generating superheated steam with a certain degree of superheat.

[0021] In the present invention, the ratio of the length L1 of the first radiation screen to the length L2 of the convection section may be 0.4-3, preferably 0.75, wherein the length refers to the radial dimension.

[0022] The ratio of the length L1 of the first radiation screen to the length L2 of the convection section may affect the heat exchange area of ​​the convection section, thereby affecting the superheat of the superheated steam generated by the convection section.

[0023] In the present invention, preferably, the first radiation screen is in an inverted T shape, and the first radiation screen comprises:

[0024] a first radiation screen end portion, the first radiation screen end portion being close to the convection section;

[0025] The first radiation screen has a belly portion, wherein the first radiation screen has a belly portion close to a central axis of the radiation waste pot cavity.

[0026] In the present invention, the distance X1 between two adjacent groups of the long radiation screens may be (0.05-0.4)D2, wherein D2 is the inner diameter of the water-cooled wall of the cylinder.

[0027] Preferably, the distance X1 between two adjacent groups of the long radiation screens ranges from 300 to 1000 mm, such as 419 mm, 628 mm, 838 mm, 977 mm, and more preferably 628 mm.

[0028] The spacing X1 refers to the distance between the front ends of two adjacent groups of the long radiation screens.

[0029] The front end refers to an end close to the central axis of the radiation waste pot cavity.

[0030] In the present invention, preferably, each group of the heat exchange units further includes one or more second radiation screens, the rear end of the second radiation screens is arranged adjacent to the cylinder water-cooled wall, and the length L4 of the second radiation screens is smaller than the length L3 of the long radiation screens.

[0031] The ratio of the length L3 of the long radiation screen to the length L4 of the second radiation screen is preferably (1.2-3):1, more preferably 2:1.

[0032] The second radiation screen may adopt a conventional heat exchanger in the art, such as a shell-and-tube type or a tube type, preferably a shell-and-tube type.

[0033] Wherein, the number of the second radiation screens included in each group of the heat exchange units is preferably 1.

[0034] Preferably, the second radiation screens and the long radiation screens of the multiple groups of heat exchange units are arranged alternately.

[0035] Among them, more preferably, the second radiation screen and the long radiation screen in each group of the heat exchange are alternately arranged and the spacing X2 between any two adjacent long radiation screens and the second radiation screen is the same, and the spacing X2 refers to the circumferential distance between the rear end of the long radiation screen and the rear end of the second radiation screen.

[0036] The distance X2 between the second radiation screen and the long radiation screen may be (0.05-0.15) D2, where D2 is the inner diameter of the water-cooled wall of the cylinder.

[0037] Preferably, the distance X2 between the second radiation screen and the long radiation screen is 300-500 mm, for example, 314 mm, 418 mm, 488 mm, more preferably 314 mm.

[0038] In the prior art, the lengths of the radiation screens in the radiation waste boiler cavity are generally the same. In order to reduce dust accumulation and slag on the radiation screens, the distance between the radiation screens is usually set larger, which results in insufficient effective heat exchange area per unit heat exchange space, low heat exchange efficiency, and inability to effectively recover heat from the synthesis gas. The present invention adopts a method of alternately arranging long and short radiation screens, which not only ensures the distance between the radiation screens, but also effectively utilizes the space of the radiation waste boiler cavity, effectively increases the heat exchange area, and improves the heat exchange efficiency.

[0039] In the present invention, preferably, the lower header of the cylinder water-cooled wall, the lower header of each group of the first radiation screen and the lower header of each group of the second radiation screen are connected to form a lower radiation header, and the lower radiation header is connected to the cooling water inlet pipe.

[0040] In the present invention, preferably, the upper header of the cylinder water-cooled wall, the upper header of each group of the first radiation screen and the upper header of each group of the second radiation screen are connected to form an upper radiation header, and the upper radiation header is connected to the outlet pipe of the saturated steam-water mixture.

[0041] In the present invention, preferably, the lower headers of each group of the convection sections are connected to form a lower convection header, and the lower convection header is connected to the air inlet pipe of the saturated steam.

[0042] In the present invention, preferably, the upper headers of each group of the convection sections are connected to form an upper convection header, and the upper convection header is connected to the outlet pipe of the superheated steam.

[0043] The saturated steam is the gas phase obtained by gas-liquid separation of the saturated steam-water mixture, and the liquid phase obtained by gas-liquid separation of the saturated steam-water mixture is mixed with external cooling water to form the cooling water.

[0044] Wherein, the upper radiation header and the upper convection header are both arranged on the top of the radiation waste pot cavity.

[0045] Wherein, the lower radiation header and the lower convection header are both arranged at the bottom of the radiation waste pot cavity.

[0046] Among them, the upper radiation header collects the saturated steam-water mixture exiting the cylinder water-cooled wall, the first radiation screen and the second radiation screen; the lower radiation header distributes the incoming cooling water to enter the cylinder water-cooled wall, the first radiation screen and the second radiation screen respectively; the upper convection header collects the superheated steam exiting the convection section; the lower convection header distributes the saturated steam to enter each heat exchange tube of the convection section respectively.

[0047] In the present invention, preferably, the novel radiation waste boiler further comprises a synthesis gas inlet, which is arranged at the top of the radiation waste boiler cavity, and the synthetic waste gas from the gasification chamber enters the radiation waste boiler cavity through the synthesis gas inlet.

[0048] In the present invention, the radiation waste pot cavity can be a combination of an upper cone and a lower cone, or a straight cylindrical structure, preferably a straight cylindrical structure.

[0049] In the prior art, the bottom of the radiation waste boiler cavity is usually provided with a constriction for introducing synthesis gas and slag into the quenching chamber. However, in actual industrial operation, slag blockage often occurs at the constriction. The radiation waste boiler cavity of the present invention preferably selects a straight-cylinder structure, which can effectively reduce the occurrence of slag blockage.

[0050] The height-to-diameter ratio H / D of the radiation waste pot cavity may be (2-20):1, preferably (3-10):1, and more preferably 4:1.

[0051] In the present invention, preferably, the radiation waste boiler further comprises a top water-cooled wall section, and the top water-cooled wall section is circumferentially arranged at the top of the radiation waste boiler cavity to form the synthesis gas inlet.

[0052] In the present invention, preferably, the radiation waste boiler also includes a quenching section, which is arranged at the bottom of the radiation waste boiler cavity, and a spray device is provided on the side of the quenching section facing the radiation waste boiler cavity, and the spray device sprays cooling medium to further cool the synthesis gas and ash.

[0053] Wherein, the spraying device includes 50 to 300 quenching water nozzles.

[0054] Furthermore, the quenching water nozzle may be a pressure swirl atomizing nozzle.

[0055] Furthermore, the outlet diameter of the quenching water nozzle may be 2 to 20 mm, preferably 5 mm.

[0056] Furthermore, the radial angle between the quenching water nozzle and the radiation waste boiler cavity can be 0 to 60 degrees, preferably 15 degrees.

[0057] Furthermore, the inlet diameter of the quenching water nozzle may be 8-20 mm, preferably 10 mm.

[0058] Furthermore, the water chamber diameter of the quenching water nozzle may be 30 to 80 mm, preferably 50 mm.

[0059] Furthermore, the outer diameter of the quenching water nozzle may be 38-88 mm, preferably 58 mm.

[0060] In the present invention, the radiation waste pot also includes a quenching chamber.

[0061] The quenching chamber may be a conventional arrangement in the art, and is generally arranged below the quenching section.

[0062] The quenching chamber is used to store spray water on the one hand, and to further solidify the liquid slag to separate it from the synthesis gas on the other hand.

[0063] The present invention also provides a gasifier comprising the above-mentioned radiation waste cooker.

[0064] The present invention also provides a system for recovering heat by utilizing the above-mentioned radiation waste pot.

[0065] The present invention also provides a process for recovering heat by utilizing the radiation waste pot.

[0066] On the basis of being in accordance with the common sense in the art, the above-mentioned preferred conditions can be arbitrarily combined to obtain the preferred embodiments of the present invention.

[0067] The reagents and raw materials used in the present invention are commercially available.

[0068] The positive and progressive effects of the present invention are:

[0069] The new radiation waste boiler provided by the present invention can generate superheated steam, and the temperature of the superheated steam can be as high as 420°C. At the same time, the water-cooling pipes that generate superheated steam are not easy to dry burn, and there is no need to set inlet and outlet pipes in the middle of the boiler, thereby overcoming the shortcomings of complex design and poor reliability. Under the condition of the same flow rate synthesis gas processing capacity, the height of the radiation waste boiler provided by the present invention can be reduced by 43% compared with the traditional radiation waste boiler, thereby greatly reducing the investment cost. BRIEF DESCRIPTION OF THE DRAWINGS

[0070] Figure 1 is a schematic cross-sectional view of a water-cooled wall body of Example 1;

[0071] Figure 2 for Figure 1 A partial enlarged view of

[0072] Figure 3 This is a schematic diagram of the radiation waste cooker application system of Example 1;

[0073] Figure 4 This is a schematic cross-sectional view of the quenching water nozzle of Example 1.

[0074] 1-syngas inlet; 2-radiation waste boiler cavity; 31-cylinder water-cooled wall; 32-convection section; 33-first radiation screen; 331-first radiation screen end; 332-first radiation screen belly; 34-second radiation screen; 35-long radiation screen; 36-heat exchange unit; 4-top water-cooled wall section; 5-quenching section; 6-quenching chamber; 7-quenching water nozzle; 81-lower radiation header; 82-upper radiation header; 83-lower convection header; 84-upper convection header; 91-cold boiler water inlet pipe; 92-boiler water inlet pipe; 93-steam-water mixture outlet pipe; 94-saturated steam inlet pipe; 95-superheated steam output pipe; 96-steam drum ;101-cold boiler water;102-synthesis gas;103-superheated steam;11-synthesis gas outlet;121-quenching water nozzle water chamber;122-quenching water nozzle inlet;123-quenching water nozzle outlet;D1-metal shell diameter;D2-cylinder water-cooled wall inner diameter;H-radiation waste boiler height;L1-first radiation screen length;L2-convection section length;L3-long radiation screen length;L4-second radiation screen length;W1-first radiation screen width;W2-convection section width;d0-quenching water nozzle outer diameter;d1-quenching water nozzle water chamber diameter;d2-quenching water nozzle inlet diameter;d3-quenching water nozzle outlet diameter. DETAILED DESCRIPTION

[0075] Reference Figure 1 and Figure 2As shown, a radiation waste boiler comprises: a cylindrical water-cooled wall 31, which is arranged along the circumferential direction of the inner wall surface of the radiation waste boiler to form a circumferentially sealed radiation waste boiler cavity 2; a plurality of groups of heat exchange units 36, which are arranged in the radiation waste boiler cavity 2 and distributed along the circumferential direction; each group of heat exchange units 36 comprises a convection section 32 and a first radiation screen 33, the convection section 32 and the first radiation screen 33 are on the same straight line, and are arranged in sequence along the central axis direction from the cylindrical water-cooled wall 31 to the radiation waste boiler cavity 2; the first radiation screen 33 and the convection section 32 of each group of heat exchange units 36 form a long radiation screen 35; the width of the first radiation screen 33 is greater than the width of the convection section 32; the width refers to the maximum size in the circumferential direction.

[0076] The first radiation screen 33 is in an inverted T-shape, and includes a first radiation screen end 331 and a first radiation screen belly 332 . The first radiation screen end 331 is close to the convection section 32 , and the first radiation screen belly 332 is close to the central axis of the radiation waste pot cavity 2 .

[0077] The spacing between two adjacent groups of long radiation screens 35 is 628 mm. Each group of heat exchange units 36 also includes a second radiation screen 34, the rear end of which is arranged adjacent to the cylinder water-cooled wall 31, and the length of the second radiation screen 34 is less than the length of the long radiation screen 35; the rear end is the end away from the central axis of the radiation waste pot cavity 2; the ratio of the length of the second radiation screen 34 to the length of the long radiation screen 35 is 2:1. The number of second radiation screens 34 in each group of heat exchange units 36 is 1; the second radiation screens 34 and the long radiation screens 35 of multiple groups of heat exchange units 36 are arranged alternately. The spacing between two adjacent second radiation screens 34 and long radiation screens 35 is 314 mm. The radiation waste pot cavity 2 has a straight cylindrical structure, and the height-to-diameter ratio of the radiation waste pot cavity 2 is 4:1.

[0078] Reference Figure 1 and Figure 3 As shown, cold boiler water 101 enters the drum 96 through the cold boiler water inlet pipe 91 as make-up water for the drum 96. The saturated steam-water mixture from the radiation waste boiler enters the drum 96 through the steam-water mixture outlet pipe 93, and the gas and liquid are separated in the drum 96. The liquid water and the cold boiler water 101 are mixed in the drum 96, and enter the lower radiation header 81 through the boiler water inlet pipe 92 under the action of gravity. The lower radiation header 81 distributes the boiler water and enters the first radiation screen 33, the cylinder water-cooled wall 31 and the second radiation screen 34 respectively. After receiving the radiation heat of the high-temperature synthesis gas, the steam-water mixture is generated, and enters the drum 96 through the steam-water mixture outlet pipe 93. The gas and liquid are separated in the drum 96, and the saturated steam enters the convection section 32 through the saturated steam inlet pipe 94. After the convection heat transfer with a relatively low heat flux density, superheated steam is generated and sent out of the boundary area through the superheated steam output pipe 95.

[0079] The synthetic waste gas from the gasification chamber of the gasifier enters the radiation waste boiler cavity 2 through the synthetic gas inlet 1, and exchanges heat with the water-cooled wall body 3 and the top water-cooled wall section 4 in the radiation waste boiler cavity 2. The temperature of the synthetic waste gas is greatly reduced after the heat exchange. A quenching water nozzle 7 is installed on the spray device of the quenching section 5. The quenching water nozzle 7 sprays quenching water to further cool the synthetic gas 102. The slag in the synthetic gas 102 is further solidified in the quenching chamber 6 and separated from the synthetic gas 102, and then output from the gasifier through the synthetic gas outlet 11.

[0080] Reference Figure 4 As shown, the chilling water enters the chilling water nozzle water chamber 121 from the chilling water nozzle inlet 122, and then enters the chilling water nozzle outlet 123 from the chilling water nozzle water chamber 121. The outlet diameter d3 of the chilling water nozzle is 5 mm, the inlet diameter d2 of the chilling water nozzle is 10 mm, the outer diameter d0 of the chilling water nozzle is 58 mm, and the water chamber diameter d1 of the chilling water nozzle is 50 mm.

[0081] The present invention is further described below by way of examples, but the present invention is not limited to the scope of the examples. The experimental methods in the following examples without specifying specific conditions are carried out according to conventional methods and conditions, or selected according to the product specifications.

[0082] Example 1

[0083] The coal-water slurry gasification unit is used for the production of chemicals. The coal processing capacity of the gasifier is 1500t / d, and the high-temperature gas flow rate from the gasifier to the radiation waste boiler is about 190000Nm 3 / h, temperature is 1340℃, ash flow rate is 6800kg / h (of which ash content is about 30%), and pressure is 6.5MPa. In order to recover the sensible heat carried by the high-temperature coal gas, a shell with an inner diameter D1 of 4200mm, an inner diameter D2 of the water-cooled wall lining of 3200mm, and a straight section height of 12m is set at the bottom of the gasification chamber. The long radiation screen and the second radiation screen are arranged at intervals, with 16 pieces in each case, and the spacing between the long radiation screens is 628mm, and the spacing between the long radiation screens and the second radiation screens is 314mm. The length ratio of the first radiation screen to the convection section is 0.75, the length ratio of the long radiation screen to the second radiation screen is 2, and the width ratio of the first radiation screen to the convection section is 4 (specifically, the first The radiation screen includes 5 water cooling tubes, 3 of which are radially distributed and 2 of which are circumferentially distributed, forming an inverted "T" shape. The convection section includes 4 radially arranged water cooling tubes. The second radiation screen includes 4 radially arranged water cooling tubes, and the diameter of the water cooling tube is 56 mm. The spray device includes 150 chilling water nozzles, and the outlet diameter of the chilling water nozzle is 5 mm. The chilling water nozzle forms an angle of 15° with the radial direction of the radiation waste pot cavity. The inlet diameter of the chilling water nozzle is 10 mm, the water chamber diameter of the chilling water nozzle is 50 mm, and the outer diameter of the chilling water nozzle is 58 mm. The detailed parameters are shown in Example 1 in the table.

[0084] Through this setting, efficient heat transfer of the waste boiler can be achieved, with the superheated steam output of 111t / h, the superheated steam temperature of 427℃, and the syngas temperature out of the waste boiler of about 685℃; the height H of the radiation waste boiler is 12m, which is 43% lower than that of the traditional radiation waste boiler.

[0085] Example 2

[0086] The spacing between the long radiation screens is changed to 419 mm, the number of long radiation screens is changed to 24 groups, the second radiation screen is not set, and the length ratio of the first radiation screen to the convection section is changed to 0.4 (specifically, the first radiation screen includes 4 water-cooling tubes, 2 of which are radially arranged and 2 are circumferentially distributed; the convection section includes 5 radially distributed water-cooling tubes), and other conditions are set the same as in Example 1.

[0087] The superheated steam output is 113t / h, the superheated steam temperature is 527℃, and the syngas temperature out of the waste boiler is about 607℃; the height H of the radiation waste boiler is 12m, which is 43% lower than that of the traditional radiation waste boiler.

[0088] Example 3

[0089] The height of the straight section of the waste boiler is 15 mm, the number of long radiation screens is changed to 12 groups, the second radiation screens are 12 groups, the spacing between the long radiation screens is 837 mm, the spacing between the long radiation screens and the second radiation screens is 418 mm, the length ratio of the first radiation screen to the convection section L1 / L2 is 0.6, and the length of the long radiation screen to the second radiation screen L3 / L4 is 1.2 (specifically, the first radiation screen includes 5 water-cooling tubes, 3 of which are radially distributed and 2 are circumferentially distributed on both sides; the convection section includes 5 radially distributed water-cooling tubes; the second radiation screen includes 4 radially distributed water-cooling tubes), and other conditions are the same as in Example 1.

[0090] The superheated steam output is about 107t / h, the superheated steam temperature is 425℃, and the temperature of the syngas out of the waste boiler is about 713℃; the height H of the radiation waste boiler is 12m, which is 43% lower than that of the traditional radiation waste boiler.

[0091] Example 4

[0092] The number of long radiation screens is changed to 16 groups, the number of second radiation screens is 16 groups, the spacing between long radiation screens is 628 mm, the spacing between the long radiation screen and the second radiation screen is 314 mm, the length ratio of the first radiation screen to the convection section L1 / L2 is 2.5, and the length between the long radiation screen and the second radiation screen L3 / L4 is 3 (specifically, the first radiation screen includes 7 water-cooling tubes, 5 of which are radially distributed and 2 are circumferentially distributed on both sides, forming an inverted "T" shape; the convection section includes 2 radially distributed water-cooling tubes; the second radiation screen includes 4 radially distributed water-cooling tubes), and other conditions are the same as in Example 1.

[0093] The superheated steam output is about 122t / h, the superheated steam temperature is 372℃, and the temperature of the syngas out of the waste boiler is about 612℃; the height H of the radiation waste boiler is 15m, which is 29% lower than that of the traditional radiation waste boiler.

[0094] Example 5

[0095] The number of long radiation screens is 9 groups, the number of second radiation screens is 9 groups, the spacing between long radiation screens is 977 mm, the spacing between the long radiation screen and the second radiation screen is 489 mm, the length ratio of the first radiation screen to the convection section L1 / L2 is 0.75, and the length between the long radiation screen and the second radiation screen L3 / L4 is 1.33 (specifically, the first radiation screen includes 5 water-cooling tubes, 3 of which are radially distributed and 2 are circumferentially distributed on both sides, forming an inverted "T" shape; the convection section includes 4 radially distributed water-cooling tubes; the second radiation screen includes 6 radially distributed water-cooling tubes), and other conditions are the same as in Example 1.

[0096] The superheated steam output is about 44t / h, the superheated steam temperature is 421℃, and the temperature of the syngas out of the waste boiler is about 848℃; the height H of the radiation waste boiler is 8m, which is 29% lower than that of the traditional radiation waste boiler.

[0097] The superheated steam output is about 44t / h, the superheated steam temperature is 421℃, and the syngas temperature out of the waste boiler is about 850℃; the height H of the radiation waste boiler is 8m, which is about 62% lower than that of the traditional radiation waste boiler.

[0098] Comparative Example 1

[0099] A conventional radiation waste boiler is used, which includes 16 groups of radiation screens, each group of radiation screens includes 5 radially distributed water-cooling pipes, and other conditions are the same as those in Example 1.

[0100] Through this setting, the waste boiler by-product saturated steam production can reach about 108t / h, and the waste boiler synthesis gas temperature can reach about 780℃.

[0101] Table 1 Parameter settings and effect data of each embodiment and comparative example

[0102]

[0103] The parameter settings of the radiation waste boilers of each embodiment and comparative example are shown in Table 1. Under the same syngas processing capacity, embodiments 1 to 5 can generate superheated steam, and the amount of superheated steam generated by embodiments 1 to 4 exceeds 100 t / h, and the superheated steam temperature is higher than 350°C, which has a high industrial application value. At the same time, the height of the radiation waste boiler is greatly reduced. The height of the waste boilers of embodiments 1 to 4 is reduced by more than 40% compared with that of comparative example 1, and the height of the radiation waste boiler of embodiment 5 is reduced by more than 60% compared with that of comparative example 1, which greatly reduces the volume of the radiation waste boiler and improves the syngas processing capacity of the radiation waste boiler per unit volume.

Claims

1. A radiation waste pot, characterized in that: It includes: A cylindrical water-cooled wall, wherein the cylindrical water-cooled wall is arranged circumferentially along the inner wall surface of the radiation waste boiler to form a circumferentially sealed radiation waste boiler cavity; A plurality of heat exchange units, wherein the plurality of heat exchange units are arranged in the radiation waste pot cavity and distributed along the circumferential direction; Each group of the heat exchange units comprises a convection section and a first radiation screen, wherein the convection section and the first radiation screen are located on the same straight line and are arranged in sequence along the central axis direction from the water-cooled wall of the cylinder to the cavity of the radiation waste boiler; The first radiation screen and the convection section of each group of the heat exchange units form a long radiation screen; The width of the first radiation screen is greater than the width of the convection section, and the ratio of the width of the first radiation screen to the width of the convection section is 3 to 7; The width refers to the maximum dimension in the circumferential direction; The ratio of the length of the first radiation screen to the length of the convection section is 0.4 to 3, and the length refers to the radial dimension; The first radiation screen is in an inverted T shape; the first radiation screen comprises a first radiation screen end and a first radiation screen belly, the end of the first radiation screen is close to the convection section, and the first radiation screen belly is close to the central axis of the radiation waste pot cavity; The spacing X1 between two adjacent groups of the long radiation screens is (0.05-0.4) D2, where D2 is the inner diameter of the water-cooled wall of the cylinder; the spacing X1 between two adjacent groups of the long radiation screens is 300-1000 mm; wherein the spacing X1 refers to the distance between the front ends of the two adjacent groups of the long radiation screens, where the front end refers to the end close to the central axis of the radiation waste boiler cavity; Each group of the heat exchange units further includes one or more second radiation screens, the rear end of the second radiation screens being arranged close to the water-cooled wall of the cylinder, and the length of the second radiation screens being less than the length of the long radiation screens; the rear end is an end away from the central axis of the radiation waste boiler cavity; the second radiation screens of the multiple groups of heat exchange units are arranged alternately with the long radiation screens; The radiation waste pot also includes: A lower radiation header, wherein the lower header of the cylinder water-cooled wall, the lower headers of each group of the first radiation screens and the lower headers of each group of the second radiation screens are connected to form the lower radiation header, and the lower radiation header is connected to a cooling water inlet pipe; An upper radiation header, the upper header of the cylinder water-cooled wall, the upper headers of each group of the first radiation screens and the upper headers of each group of the second radiation screens are connected to form the upper radiation header, and the upper radiation header is connected to the outlet pipe of the saturated steam-water mixture; A lower convection header, wherein the lower headers of the convection sections of each group are connected to form the lower convection header, and the lower convection header is connected to an air inlet pipe of saturated steam; An upper convection header, the upper headers of each group of the convection sections are connected to form the upper convection header, and the upper convection header is connected to the outlet pipe of the superheated steam.

2. The radiation waste cooker according to claim 1, characterized in that: The ratio of the width of the first radiation screen to the width of the convection section is 4; And / or, the ratio of the length of the first radiation screen to the length of the convection section is 0.75, and the length refers to the radial dimension.

3. The radiation waste cooker according to claim 1, characterized in that: The distance between two adjacent groups of the long radiation screens is 419 mm, 628 mm, 838 mm or 977 mm.

4. The radiation waste cooker according to any one of claims 1 to 3, characterized in that: The ratio of the length of the long radiation screen to the length of the second radiation screen is (1.2-3):

1.

5. The radiation waste cooker according to claim 4, characterized in that: The ratio of the length of the long radiation screen to the length of the second radiation screen is 2:

1.

6. The radiation waste cooker according to claim 4, characterized in that: The distance between two adjacent second radiation screens and the long radiation screens is (0.05-0.15) D2, where D2 is the inner diameter of the water-cooled wall of the cylinder; and / or, the distances between any two adjacent long radiation screens and the second radiation screen are the same; And / or, the radiation waste pot cavity is a combination of an upper cone and a lower cone or a straight cylindrical structure; And / or, the height-to-diameter ratio of the radiation waste pot cavity is (2-20):

1.

7. The radiation waste cooker according to claim 6, characterized in that: The distance between two adjacent second radiation screens and the long radiation screens is 300-500 mm; And / or, the radiation waste pot cavity is a straight cylindrical structure; And / or, the height-to-diameter ratio of the radiation waste pot cavity is (3-10):

1.

8. The radiation waste cooker according to claim 7, characterized in that: The distance between two adjacent second radiation screens and the long radiation screens is 314 mm, 418 mm or 488 mm; And / or, the height-to-diameter ratio of the radiation waste pot cavity is 4:

1.

9. The radiation waste cooker according to claim 1, characterized in that: The radiation waste pot further comprises a quenching section, which is arranged at the bottom of the radiation waste pot cavity, and 50-300 quenching water nozzles are arranged on the quenching section; The quenching water nozzle is a pressure swirl atomizing nozzle; The outlet diameter of the quenching water nozzle is 2 to 20 mm; The quenching water nozzle forms an angle of 0 to 60 degrees with the radial direction of the radiation waste boiler cavity; The inlet diameter of the quenching water nozzle is 8 to 20 mm; The water chamber diameter of the quenching water nozzle is 30 to 80 mm; The outer diameter of the quenching water nozzle is 38-88 mm.

10. A gasifier, characterized in that: It comprises the radiation waste pot as described in any one of claims 1 to 9.

11. A heat recovery system, characterized in that: The method utilizes the radiation waste pot described in any one of claims 1 to 9 to recover heat.

12. A heat recovery process, characterized in that: The method utilizes the radiation waste pot described in any one of claims 1 to 9 to recover heat.

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