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Nuclear energy coupling chemical energy power generation system and method based on two-loop boiler

A technology of chemical energy and boiler, applied in the field of nuclear energy coupling chemical energy power generation system, can solve the problems of coupled boiler design and operation safety, low steam grade, low power generation efficiency, etc., to improve cycle thermal efficiency and power generation efficiency , fast load response, and the effect of improving safety

Active Publication Date: 2019-01-11
SHANDONG ELECTRIC POWER ENG CONSULTING INST CORP
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0005] In order to solve the above problems, the present invention proposes a system and method for nuclear energy coupled chemical energy power generation based on a two-circuit boiler. The problem of boiler design and operation safety cannot be guaranteed, and it can also solve the load impact problem on the nuclear island and boiler when the load is lifted and lowered during the operation of the coupling system

Method used

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  • Nuclear energy coupling chemical energy power generation system and method based on two-loop boiler
  • Nuclear energy coupling chemical energy power generation system and method based on two-loop boiler

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Effect test

Embodiment 1

[0042] In one or more embodiments, a nuclear energy coupled chemical energy power generation system based on a two-circuit boiler is disclosed, such as figure 1 As shown, it includes: nuclear island 1, boiler 11, gas-molten salt heat exchanger 9, hot molten salt tank 6, cold molten salt tank 7, cold molten salt pump 8, hot molten salt pump 12 for superheated steam, reheating Hot molten salt pump for steam 13, molten salt-superheated steam heat exchanger 4, molten salt-reheated steam heat exchanger 5, steam turbine with base load 2, first generator 3, coupling steam turbine, second generator 18 , Low pressure heater, high pressure heater 14, deaerator 19, condenser 23, cooling tower 26, circulating water pump 24, feed water pump 20, etc.

[0043] The nuclear island 1 includes a nuclear reactor 1-1, a primary circuit main pump 1-3 of the nuclear island, a steam generator 1-2, and the like. The feed water entering the nuclear island 1 is heated by the steam generator 1-2 and the...

Embodiment 2

[0064] In one or more embodiments, a nuclear energy coupled chemical energy power generation system based on a two-circuit boiler is disclosed, such as figure 2 As shown, it includes: nuclear island 1, boiler 11, gas-molten salt heat exchanger 9, hot molten salt tank 6, cold molten salt tank 7, cold molten salt pump 8, hot molten salt pump 12 for superheated steam, molten salt - superheated steam heat exchanger 4, steam turbine with base load 2, first generator 3, coupling steam turbine, second generator 18, low pressure heater, high pressure heater 14, deaerator 19, condenser 23, cooling Tower 26, circulating water pump 24, feed water pump 20, etc.

[0065] The nuclear island 1 includes a nuclear reactor 1-1, a primary circuit main pump 1-3 of the nuclear island, a steam generator 1-2, and the like. The feed water entering the nuclear island 1 is heated by the steam generator 1-2 and then evaporated into saturated steam or wet steam with a dryness greater than 0.9.

[0066...

Embodiment 3

[0086] In one or more embodiments, a method for nuclear energy coupled chemical energy power generation based on a two-circuit boiler is disclosed, including: the boiler 11 burns chemical energy fuels (fossil fuels such as coal, oil, natural gas, etc., and biomass, Garbage and other renewable energy fuels, etc.) convert chemical energy into thermal energy, and transfer the thermal energy through special gases (such as helium, supercritical carbon dioxide, etc.), and the low-temperature gas (such as helium with a temperature below 500°C) at the boiler inlet Gas or supercritical carbon dioxide, etc.), the boiler outlet is high-temperature gas (such as helium or supercritical carbon dioxide with a temperature range of 500-700 ° C), and the gas circulation power is provided by the gas circulation fan 10 located at the boiler inlet.

[0087] The feed water enters the nuclear island 1 after being heated in the high-pressure heater 14, and is heated and evaporated in the nuclear islan...

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Abstract

The invention discloses a nuclear energy coupling chemical energy power generation system and method based on a two-loop boiler. The boiler is connected with a gas-fused salt heat exchanger, and a first boiler loop is formed; the gas-fused salt heat exchanger is connected with a cold fused salt tank and a hot fused salt tank, the cold fused salt tank and the hot fused salt tank are correspondinglyconnected with a fused salt-superheated steam heat exchanger, and a second boiler loop is formed; a steam outlet of a nuclear island is divided into two ways; one way is connected with a steam turbine with a basic load, and the other way is connected with a fused salt-superheated steam heat exchanger; a steam outlet of the fused salt-superheated steam heat exchanger is connected with a steam turbine for coupling; the steam turbine with the basic load drives a first power generator to generate power; and the steam turbine for coupling drives a second power generator to generate power. The nuclear energy coupling chemical energy power generation system and method based on the two-loop boiler fully utilizes the characteristics that special gas is high in specific heat capacity and fused saltaccumulates heat so that the process time can be subjected to translation, and the running safety and the adaptability to the variable work condition of the coupling system are improved while the thermal cycle efficiency and the power generating efficiency are improved.

Description

technical field [0001] The invention relates to the field of energy technology, in particular to a system and method for nuclear energy coupling chemical energy power generation based on a two-circuit boiler. Background technique [0002] Pressurized water reactors are the mainstream technology for modern commercial nuclear power. A conventional pressurized water reactor is generally a two-circuit system, in which the steam in the two-circuit system drives a steam turbine to generate electricity. Due to the limitation of the temperature of the reactor heat carrier (the average outlet temperature of the pressurized water reactor is generally lower than 330 degrees Celsius), only low-pressure (5.0-8.0MPa) saturated steam or slightly superheated (20-30 degrees Celsius) steam can be produced , the ideal specific enthalpy drop of the whole machine is very small, and the steam humidity is high. In order to increase the power of a single machine, the steam flow rate must be large....

Claims

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Application Information

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IPC IPC(8): F01D15/10F01K7/32F01K11/00F01K13/00F01K25/10
CPCF01D15/10F01K7/32F01K11/00F01K13/00F01K25/10F01K25/103
Inventor 刘义达祁金胜杨俊波王龙林
Owner SHANDONG ELECTRIC POWER ENG CONSULTING INST CORP
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