JP2009115571A - Renewed abwr adapted to combined power generation - Google Patents

Abstract

<P>PROBLEM TO BE SOLVED: To improve power generation efficiency by renewing a current advanced boiling water reactor (ABWR) by modifying it not on a large scale. <P>SOLUTION: Further power generation through the agency of a steam turbine (41) with high-pressure saturated steam (23) produced by cooling high-pressure superheated steam (24) during a power generation process in a newly laid electrothermal semiconductor (100) after generating power with the electrothermal semiconductor (100) by producing the high-pressure superheated steam (24) through some modification of a licensed ABWR leads to combined power generation to improve the power generation efficiency. <P>COPYRIGHT: (C)2009,JPO&INPIT

Description

  The present invention relates to an in-core structure of an improved boiling water reactor (ABWR) that uses light water as a coolant, and a thermoelectric semiconductor.

FIG. 1 is a schematic diagram of power generation via a steam turbine (41) using a conventional ABWR as a high-temperature heat source. Non-patent document 1, non-patent document 3, non-patent document 3, and non-patent document 4 were supplemented mainly by non-patent document 1. In a pressure vessel (10) containing nuclear fuel, a cylindrical shroud (11), a core plate (9) that supports the lateral direction of the reactor, and a nuclear fuel assembly in which a large number of nuclear fuel rods containing nuclear fuel are bundled ( 2) Built-in reactor structures such as a control rod (3), a steam separator (12) and a dryer (13) formed by cross-molding a neutron absorber for adjusting the reactor power . A control rod drive (5) for operating the control rod (3) up and down via a control rod extension rod (4) fixed to the tip of the control rod (3) is attached to the outer lower part of the pressure vessel (10). An internal pump (7) for driving a rotor blade (6) for circulating water in order to remove heat generated in the nuclear fuel is installed.
The steam of the high-pressure saturated steam (23) generated by the heat of the nuclear fuel assembly (2) passes through several high-pressure steam pipes (31) and goes out to the steam turbine (41) in the direction of the arrow. The steam turbine (41) rotates the generator (42) to generate electric power. The moist and low-temperature steam that has finished work in the steam turbine (41) is cooled by the condenser (43) to become liquid water, which is pressurized by the feed water booster pump (30) and several high-pressure feed pipes (32) It passes through the pressure vessel (10) in the direction of the arrow and becomes the feed water flow rate. The feed water flow rate, which is liquid water, is mixed with high-temperature water in the gap region (14) between the shroud (11) and the pressure vessel (10) to become high-pressure unsaturated water (21), and the high-pressure unsaturated water (21) rotates. It is made high-speed by the blade (6) and flows into the nuclear fuel assembly (2) from the lower part of the core plate (9) as the core flow rate. The core flow rate is about 5 times the feed water flow rate. The high-pressure unsaturated water (21) receives heat from the nuclear fuel assembly (2) and becomes a high-pressure two-phase flow (22). The high-pressure two-phase flow (22) is separated into liquid water and high-humidity vapor by the steam separator (12). Steam flow rate of high-pressure saturated steam (23). The steam flow rate is almost the same as the feed water flow rate. About 4/5 of the core flow returns as hot water in the gap region (14). The high-pressure saturated steam (23) exiting the dryer (13) exits to the steam turbine (41) as a steam flow rate.
ABWR uses steam generated in the Rankine cycle with high-temperature and high-pressure saturated steam (23) as a high-temperature heat source and low-temperature and low-pressure water in the condenser (43) as a low-temperature heat source due to the heat generated by the nuclear fuel in the pressure vessel (10). By rotating the turbine (41), the generator (42) is rotated to generate electricity.
In recent years, the ABWR core design has come out with the prospect of a reduced-speed spectrum core (Non-Patent Document 5). Reduce the core flow rate to about twice the steam flow rate. Thermal removal of nuclear fuel rods is possible by natural circulation. The nuclear fuel assemblies (2) are densely loaded with nuclear fuel rods to increase the number. The height of the nuclear fuel rods is lowered to make the total heat transfer area of all the nuclear fuel rods comparable to that of the conventional ABWR. Since the core flow rate has decreased, the flow resistance is reduced, and natural circulation is possible. Furthermore, even if the core flow rate is about the same as the steam flow rate, no problem will occur. ABWR's coolant is pure water, so there are few impurities, and even if the upper part of the nuclear fuel assembly (2) is only steam, the problem of scale is considered to be minor.
: Nuclear Industry, 1992, Ministry of International Trade and Industry, 3rd Generation, “Improvement of Standardization and Advancement”. : Ohm, 1989, “Nuclear Handbook”. : TEPCO, 1993, “Overview of improved BWR”. : Dobunshoin, 1988, Akiyama "Light Water Reactor". : Japan Atomic Energy Research Institute, 2002, edited by Nakano et al.

Like most nuclear reactors, the thermal efficiency of ABWR is about 33%. The steam generated in ABWR is high-pressure saturated steam (23) at 70 atm and about 286 ° C, so it is difficult to further increase the thermal efficiency.
We want to increase the thermal efficiency and lower the power generation cost while lowering the construction cost of ABWR.
In thermal power generation in which fossil fuel is burned, the efficiency is generally increased by combined power generation in which another cycle is added to the Rankine cycle or Brayton cycle. The Rankine cycle or Brayton cycle alone will not increase the efficiency unless it is made at a very high temperature and pressure.
Many problems arise due to material limitations in generating electricity in a high-temperature and high-pressure Rankine cycle or Brayton cycle by burning nuclear fuel.

The pressure in the pressure vessel (10) is maintained at about 70 atm, similar to the conventional ABWR.
The core flow rate is the same as the steam flow rate, and the high temperature superheated steam (24) is used for the core upper coolant.
When the core flow rate is lowered, the flow resistance is reduced, so the internal pump motor (7) and the rotor blade (6) for increasing the circulation force become unnecessary and are eliminated.
Since the upper core coolant has become high-pressure superheated steam (24), the steam separator (12) and dryer (13) are no longer necessary and will be deleted.
A large number of thermoelectric semiconductor built-in water supply pipes (132) branched from the high-pressure water supply pipe (32) are extended to the gap region (14) through the upper side where the dryer (13) was, and the thermoelectric semiconductor built-in water supply pipe (132) After generating electricity with a thermoelectric semiconductor (100) with a melting point of 286 ° C or higher, the high-pressure superheated steam (24) is converted into conventional ABWR steam by high-pressure saturated steam (23) cooled by the thermoelectric semiconductor built-in water supply pipe (132). The ABWR is renewed to the combined power generation that also generates electricity through the turbine (41).
A lead-type reactor (299) that contains MOX (mixed oxide of plutonium and uranium) in a low-pressure heat-resistant vessel (201) with a nuclear fuel assembly (2) contained in the low-pressure heat-resistant vessel (201) is a lead-type reactor. A high-temperature thermoelectric semiconductor with a melting point of 286 ° C or higher installed in a low-pressure lead pipe (231) that connects the steam generator (399) and the lead-type reactor (299) that generate steam with high-temperature molten lead from the reactor (299) A combined power generator that generates electric power through the steam turbine (41) by high-pressure and high-temperature steam generated by the steam generator (399) after generating power in (101).
Low pressure lead piping connecting the lead temperature reactor (299) and the lead temperature reactor (299) with the lead reactor (299) as a high-temperature heat source and the gas temperature riser (499) that raises the gas temperature with high-temperature molten lead from the lead reactor (299) Combined power generation that generates power via a gas turbine (259) using gas heated by a gas heater (499) after generating electricity with a high-temperature thermoelectric semiconductor (101) with a melting point of 286 ° C or higher laid on (231) apparatus.
A combined power generation device that generates power through a steam turbine (41) or a gas turbine (259) after generating power from a thermoelectric semiconductor having a melting point of 286 ° C. or higher, using fossil fuel combustion or nuclear fuel combustion as a high-temperature heat source.

Prior to power generation via the steam turbine (41) by the high pressure saturated steam (23) of the conventional ABWR, the temperature of the high pressure superheated steam (24) and the high pressure and low temperature water flowing in the thermoelectric semiconductor built-in water supply pipe (132) Combined power generation can be carried out by the power generation of the thermoelectric semiconductor (100) using the difference, and the power generation cost can be reduced.
Moreover, since the pressure in the pressure vessel (10) was maintained at about 70 atm, the same as the conventional ABWR, the pressure vessel (10) with built-in reactor structure was not significantly improved. And licensing costs will not increase significantly.
The internal pump motor (7), the rotor blade (6), the steam separator (12) and the dryer (13) could be deleted, which led to a reduction in construction costs and periodic inspection costs, resulting in a reduction in power generation costs.
Lead reactor (299) containing nuclear fuel in a heat-resistant vessel (201) instead of a pressure vessel (10) using lead with low vapor pressure as a coolant for the reactor as a high-temperature heat source, from the lead reactor (299) After generating electricity with the high-temperature thermoelectric semiconductor (101) installed in the low-pressure lead pipe (231) connecting the steam generator (399) and the lead-type reactor (299) that generate steam with high-temperature molten lead, the steam generator ( 399) can be combined with the high-pressure and high-temperature steam generated through the steam turbine (41) to reduce power generation costs.
Since the pressure in the heat-resistant vessel (201) is low, even if various pipes installed in the lead reactor (299) are broken, molten lead as a coolant does not decrease rapidly, which hinders heat removal from the nuclear fuel rods. The degree of causing damage is small and the safety is high.
Low pressure lead piping connecting the lead temperature reactor (299) and the lead temperature reactor (299), which uses the lead reactor (299) as a high-temperature heat source and increases the gas temperature with high-temperature molten lead from the lead reactor (299) After generating power with the high-temperature thermoelectric semiconductor (101) laid on (231), combined power generation can be performed with the gas heated by the gas heater (499) via the gas turbine (259). Reduced. .
Even in thermal power generation that burns fossil fuels, combined power generation can be performed by generating power with high-temperature thermoelectric semiconductor (101) before generating power via steam turbine (41) or gas turbine (259), and power generation costs can be reduced. Is self-explanatory.
Since the combined power generation has improved the thermal efficiency, the heat released to the external environment is reduced and global warming can be reduced.

  We were able to provide a renewed ABWR with low power generation costs.

FIG. 2 is a schematic diagram of an ABWR that has been renewed into a combined power generation system that generates power using the thermoelectric semiconductor (100) and also generates power via the steam turbine (41) according to the present invention. Various arrows in the figure indicate the direction of fluid flow.
By maintaining the pressure in the pressure vessel (10) at about 70 atm as in the case of the conventional ABWR, the pressure vessel (10) can be used as it is for the material, thickness and shape of the pressure vessel (10). As a result, new additional costs such as development costs, design costs, and application costs can be prevented.
The flow resistance was reduced by reducing the core flow rate to the same as the steam flow rate, so that the nuclear fuel rods could be removed with only natural circulation force. Therefore, the internal pump motor (7) and the rotor blade (6) for increasing the circulation force are no longer necessary and have been deleted.
Since the upper core coolant became high-pressure superheated steam (24), the steam separator (12) and dryer (13) became unnecessary and were deleted.
The liquid water at the feed flow rate that has returned to the pressure vessel (10) through the high-pressure feed pipe (32) enters a large number of thermoelectric semiconductor built-in feed pipes (132) branched from the high-pressure feed pipe (32). While passing the upper side where the dryer (13) was present, it is heated by the high-pressure superheated steam (24) at the upper part of the core and released into the gap region (14) between the shroud (11) and the pressure vessel (10). The water released into the gap region (14) is mixed with the high temperature water in the gap region (14) to become high-pressure unsaturated water (21). High-pressure unsaturated water (21) flows into the nuclear fuel assembly (2) from the lower part of the core plate (9) at a core flow rate. The high-pressure unsaturated water (21) receives heat from the nuclear fuel assembly (2) and becomes a high-pressure two-phase flow (22). The high-pressure two-phase flow (22) further receives heat from the nuclear fuel assembly (2) and becomes the same high-pressure saturated steam (23) as about 286 ° C. The high-pressure saturated steam (23) further receives heat from the nuclear fuel assembly (2) and becomes high-pressure superheated steam (24). The steam temperature will be higher than 286 ° C. The core flow rate of the high-pressure unsaturated water (21) that flows into the high-pressure superheated steam (24) flows, and then is cooled while passing through the gaps between the multiple thermoelectric semiconductor built-in water supply pipes (132). It flows into the steam turbine (41) as a conventional steam flow rate. Due to the difference between the density of the high-pressure unsaturated water (21) and the density of the high-pressure two-phase flow (22) in the nuclear fuel assembly (2), the coolant gains circulation power.
By using densely loaded nuclear fuel rods on the nuclear fuel assembly (2) and increasing the number of nuclear fuel rods to reduce the height of the nuclear fuel rods, the total heat transfer area of all nuclear fuel rods is about the same as that of the conventional ABWR. It is. Since the core flow rate was lowered to the same level as the steam flow rate, the flow resistance decreased. Since the removal of the rotary blade (6), the steam separator (12) and the dryer (13) eliminates the flow resistance, the circulating force of the coolant increases. As a result, it is considered that heat can be removed from the nuclear fuel rod even in natural circulation. Although the coolant temperature above the nuclear fuel assembly (2) is higher than the conventional 286 ° C., there is no problem. That is, the upper neutron flux near the upper end of the core leaks to the upper part, so it is quite small, and the power generated by the reaction between the neutron flux and nuclear fuel is small at the upper part of the nuclear fuel assembly (2), so the temperature of the nuclear fuel rod rises excessively. Never do.
A thermoelectric semiconductor built-in water supply pipe (132) through which high-pressure low-temperature liquid feed water flows contains a thermoelectric semiconductor (100) having a melting point of 286 ° C. or higher. Electric power is generated in the Carnot cycle of the thermoelectric semiconductor (100) using the high pressure superheated steam (24) as a high temperature heat source and the feed water as a low temperature heat source. The high-pressure superheated steam (24) is cooled by the thermoelectric semiconductor built-in water supply pipe (132) to become high-pressure saturated steam (23), and the high-pressure saturated steam (23) is also generated through the steam turbine (41) as usual. ABWR is renewed for combined power generation.
Since the cooling water of ABWR is pure water and has high electrical insulation, it is not a problem to incorporate the thermoelectric semiconductor (100) in the thermoelectric semiconductor built-in water supply pipe (132). Electricity generated in the thermoelectric semiconductor (100) is taken out from the terminal (103) through the high-pressure water supply pipe (32).
The steam / water separator (12) and the dryer (13) are removed, and the surface of the thermoelectric semiconductor built-in water supply pipe (132) is exposed to the high-pressure superheated steam (24), so that heat can be easily input to the thermoelectric semiconductor (100).
The performance Z of a thermoelectric semiconductor that generates electricity by the Seebeck effect can be expressed as Z = (α ² / ρ) / κ where α is the Seebeck coefficient, ρ is the electrical resistivity, and κ is the thermal conductivity (Non-patent Document 6). . Although it is desirable that Z is large for the thermoelectric semiconductor (100), in the present invention, since power is also generated through the steam turbine (41) after power generation by the thermoelectric semiconductor (100), Z is small as a result of large κ. A thermoelectric semiconductor can also be used. Even if the heat leakage from the thermoelectric semiconductor (100) is large in proportion to κ, the heat is recovered and converted to electricity through the steam turbine (41). Therefore, the thermoelectric semiconductor (100) only needs to have a large (α ² / ρ). An alloy of silicon and germanium (SiGe) with boron (B) or phosphorus (P) added, or iron silicide (FeSi ₂ ) with manganese (Mn), aluminum (Al) or cobalt (Co) added at high temperatures It is a thermoelectric semiconductor with a large (α ² / ρ). Furthermore, since the rear steam turbine (41) recovers exhaust heat from the thermoelectric semiconductor (100), it is only necessary to be a thermoelectric semiconductor having a large α. Even if ρ is large and the internal heat generation of the thermoelectric semiconductor is large, the heat is recovered. Thermoelectric semiconductors with a large α include n-type, −700 μV / K, 1 copper oxide (CuO), and p-type, +1000 μV / K, 2 copper oxide (Cu ₂ O).
Since thermoelectric semiconductors can generate electricity without moving parts, they can generate electricity at high temperatures near the melting point.
Since power generation by a thermoelectric semiconductor is based on a Carnot cycle that works between a high-temperature heat source and a low-temperature heat source, most of the efficiency is determined by the temperature ratio between the high-temperature temperature and the low-temperature temperature. Therefore, the temperature of the coolant at the top of the core was raised from the conventional high-pressure saturated steam (23) to the high-pressure superheated steam (24).
If the core flow rate is made the same as the steam flow rate of the conventional ABWR and the heat output is made larger than that of the conventional ABWR, the temperature of the high pressure superheated steam (24) becomes higher than the temperature of the high pressure saturated steam (23). After the high pressure superheated steam (24) is generated by the thermoelectric semiconductor (100), the flow rate of the high pressure saturated steam (23) cooled by the thermoelectric semiconductor built-in water supply pipe (132) is the same as the steam flow rate of the conventional ABWR. The amount of power generated through the turbine (41) is the same as that of the conventional ABWR. The combined power generation amount is larger than the power generation amount of the conventional ABWR by the amount generated by the thermoelectric semiconductor (100).
High pressure superheated steam (24) can be generated even if the heat output is the same as that of the conventional ABWR and the core flow rate is lower than the steam flow rate of the conventional ABWR. The high-pressure superheated steam (24) cooled by the thermoelectric semiconductor built-in water supply pipe (132) after being generated by the thermoelectric semiconductor (100) becomes high-pressure saturated steam (23) .In the present invention, the core flow rate, feed water flow rate, and steam flow rate are changed. Since the flow rate of the high-pressure saturated steam (23) is lower than the steam flow rate in the conventional ABWR, the power generation amount through the steam turbine (41) is lower than that in the conventional ABWR. However, the combined power generation amount that is the sum of the power generation amount in the thermoelectric semiconductor (100) and the power generation amount through the steam turbine (41) exceeds the power generation amount of the conventional ABWR.
In the conventional ABWR, the feed water is heated using several feed water adders, but in the present invention, it is heated while passing through the thermoelectric semiconductor built-in water supply pipe (132) in the process of generating electricity with the thermoelectric semiconductor (100). Therefore, the water heater can be unnecessary or reduced. Construction cost will be reduced.
The internal pump motor (7), rotor blade (6), steam separator (12), and dryer (13) could be deleted, resulting in a reduction in construction costs and periodic inspection costs. did it.
: Nikkan Kogyo Shimbun, 1988, “Thermoelectric semiconductors and their applications” by Uemura et al.

A combined power generation system using a nuclear reactor that is considered to have a low pressure and a relatively high safety by applying the first embodiment will be described below.
Fig. 3 shows a lead-type nuclear reactor (299) in which a nuclear fuel assembly (2) containing MOX (mixed oxide of plutonium and uranium) is incorporated in a low-pressure heat-resistant vessel (201) and lead is used as a coolant. A melting point of 286 was laid in the low-pressure lead pipe (231) connecting the steam generator (399) and the lead reactor (299), which generates steam with high-temperature molten lead from the lead reactor (299) as a high-temperature heat source. FIG. 2 is a schematic diagram of a combined power generation apparatus that generates power using a high-pressure high-temperature steam generated by a steam generator (399) and also generates power via a steam turbine (41) after generating power with a high-temperature thermoelectric semiconductor (101) at a temperature of ℃ or higher.
The reactor is made of fast neutrons because lead is used as a coolant because it has a small neutron absorption effect and a small neutron moderation effect. We loaded a nuclear fuel assembly (2) that uses plutonium (Pu), which has high combustion efficiency for fast neutrons, and high decay heat, and MOX, which is a mixed oxide of uranium (U). Even if the reactor shuts down, the molten liquid state can be maintained without solidifying lead by the decay heat of Pu.
Since the vapor pressure of lead is low, the lead-type reactor (299) can incorporate the nuclear fuel assembly (2) in the low-pressure heat-resistant vessel (201).
A cylindrical partition wall (202) corresponding to the shroud (11) in ABWR was laid inside the low pressure heat resistant container (201). The space between the low-pressure heat-resistant container (201) and the partition wall (202) is filled with low-pressure low-temperature molten lead (205), and the low-pressure low-pressure lead pipe (231 ). A heat shielding plate (203) is laid inside the partition wall (202) to protect the partition wall (202) from low-pressure high-temperature molten lead (206).
Low-temperature and low-pressure molten lead from the low-pressure lead supply pipe (231) enters the nuclear fuel assembly (2) from under the core plate (9), receives heat from the nuclear fuel assembly (2), and low-pressure high-temperature molten lead (206) It hits the upper grid plate (207) and goes out of the low-pressure heat-resistant container (201) from the low-pressure high-temperature lead pipe (232). The low-pressure high-temperature molten lead (206) passing through the low-pressure high-temperature lead pipe (232) reaches the low-pressure heat-resistant container 2 (241) of the steam generator (399) filled with the low-pressure high-temperature molten lead 2 (246). Low-pressure high-temperature molten lead 2 (246) is cooled by a high-pressure capillary (225) to become low-pressure low-temperature molten lead 2 (245), and low-pressure low-temperature molten lead 2 (245) is sucked up by a lead feed pump (230) Return to the inside of the low-pressure heat-resistant vessel (201) of the lead-type reactor (299) through (231). The partition wall 2 (242) separates the low-pressure high-temperature molten lead 2 (246) from the low-pressure low-temperature molten lead 2 (245) so that the temperature does not become uniform.
The water cooled by the condenser (43) and turned into liquid passes through the high-pressure water supply pipe (32), and the high-pressure low-temperature water header (223) in the low-pressure heat-resistant container 2 (241) of the steam generator (399). The high pressure and low temperature water header (223) branches into a number of high pressure thin tubes (225) and receives heat from the low pressure and high temperature molten lead 2 (246) to become high pressure and high temperature steam. Enter and exit from the high pressure steam pipe (31) to the steam turbine (41). The steam turbine (41) rotates the generator (42) to generate power. Steam that has finished working in the steam turbine (41) is cooled by the condenser (43) to become liquid water.
The operation of the control rod (3) is caused by the vertical movement of the control rod support rod (4) fixed to the control rod (3). The control rod support rod (4) passes through the upper lid (208) and is coupled to the upper control rod drive (211).
A space between the upper lid (208) and the upper lattice plate (207) is filled with a low pressure gas (204) made of low pressure argon gas or carbon dioxide gas.
The replacement of the nuclear fuel assembly (2) is performed in an open space by removing the upper lid (208) and the upper lattice plate (207). Lead is easy to handle because of its weak activity against air and water. A mixture of lead and bismuth can be considered as the low-melting point metal coolant, but bismuth becomes polonium that absorbs neutrons and emits α rays, so that it is difficult to handle in an open space.
A high temperature thermoelectric semiconductor (101) was laid on the surface of the low pressure lead pipe (231). The high-temperature thermoelectric semiconductor (101) generates electricity by using radiant heat from the surface of the low-pressure high-temperature lead pipe (232) as a high-temperature heat source and using the surface of the low-pressure lead-feed pipe (231) as a low-temperature heat source.
The present invention is a combined power generator that generates power with a high-temperature thermoelectric semiconductor (101) before power generation via a steam turbine (41). The exhaust heat of the high-temperature thermoelectric semiconductor (101) is recovered by heating the low-pressure and low-temperature lead flowing through the low-pressure lead supply pipe (231).
Since the rear steam turbine (41) recovers the exhaust heat of the high temperature thermoelectric semiconductor (101), the high temperature thermoelectric semiconductor (101) only needs to have a large (α ² / ρ) or α.
When the reactor is shut down, if it is used as a heater by energizing the high-temperature thermoelectric semiconductor (101) installed in the low-pressure lead supply pipe (231), the lead in the low-pressure lead supply pipe (231) is in a molten liquid state without solidifying. Is preserved.
If a high-temperature thermoelectric semiconductor (101) is also laid on the surface of the low-pressure high-temperature lead pipe (232) opposite to the low-pressure lead-supply pipe (231), the low-pressure high-temperature lead pipe ( The lead in 232) remains in a molten liquid state without solidifying. During normal operation, power is also generated using the external atmosphere as a low-temperature heat source.
As a countermeasure against breakage of the high pressure thin tube (225), a pressure relaxation cylinder (247) was provided on the upper portion of the steam generator (399).
The high pressure steam released when the high pressure thin tube (225) breaks is discharged from the steam relief valve (248) into the atmosphere outside the steam generator (399), and the soundness of the steam generator (399) is maintained. Since the proportion of molten lead splashing reaches the height of the steam relief valve (248) is small, lead is not easily released into the external atmosphere.
Since the coolant temperature of the fast breeder reactor using sodium as the coolant is about 550 ° C, it is considered that a coolant temperature of about 550 ° C is possible even in the lead reactor (299). Therefore, if the high temperature thermoelectric semiconductor (101) having a melting point of 550 ° C. or higher is used, the thermal efficiency is remarkably improved. In the fast breeder reactor, high-temperature and high-pressure superheated steam is generated by a steam generator.

The steam generator (399) in the second embodiment is replaced with a gas temperature riser (499), and electric power is generated via the gas turbine (259) using the working fluid as a gas.
FIG. 4 shows a gas heater (499) and a lead reactor (299) that use a lead reactor (299) as a high-temperature heat source and increase the gas temperature with high-temperature molten lead from the lead reactor (299). ) Is connected to the low-pressure lead pipe (231) connecting the gas turbine (259) with the gas heated by the gas heater (499) after generating electricity with the high-temperature thermoelectric semiconductor (101) with a melting point of 286 ° C or higher. FIG.
The low-pressure and low-temperature gas cooled by the cooler (260) is pressurized by the gas compressor (258) to become a high-pressure and low-temperature gas. The high-pressure and low-temperature gas enters the high-pressure and low-temperature gas header (253) in the low-pressure heat-resistant container 2 (241) of the gas heater (499) from the high-pressure and low-temperature gas supply pipe (252). ) Enters a number of high-pressure capillaries (225) that branch off from the low-pressure and high-temperature molten lead 2 (246) to become high-pressure and high-temperature gas, enters the high-pressure and high-temperature gas header (254), and enters the high-pressure and high-temperature gas pipe (251) Go out to the gas turbine (259). The generator (42) is rotated by the gas turbine (259) to generate electricity. The gas that has become low-pressure and low-temperature after finishing work in the gas turbine (259) is cooled by the cooler (260) to become low-pressure and low-temperature gas.
A high temperature thermoelectric semiconductor (101) was laid on the surface of the low pressure lead pipe (231). The high temperature thermoelectric semiconductor (101) generates electricity using the radiant heat from the low pressure high temperature lead pipe (232) as a high temperature heat source and the low pressure lead supply pipe (231) as a low temperature heat source.
The present invention is a combined power generation apparatus that generates power with a high-temperature thermoelectric semiconductor (101) before power generation via a gas turbine (259). The exhaust heat of the high-temperature thermoelectric semiconductor (101) is recovered by heating the low-pressure and low-temperature lead flowing through the low-pressure lead supply pipe (231).
When the reactor is shut down, if it is used as a heater by energizing the high-temperature thermoelectric semiconductor (101) installed in the low-pressure lead supply pipe (231), the lead in the low-pressure lead supply pipe (231) is in a molten liquid state without solidifying. Is preserved.
If a high-temperature thermoelectric semiconductor (101) is installed on the surface of the low-pressure high-temperature lead pipe (232) opposite to the low-pressure lead-feed pipe (231), the low-pressure high-temperature lead pipe ( The lead in 232) remains in a molten liquid state without solidifying. During normal operation, power is also generated using the external atmosphere as a low-temperature heat source.
Since the rear gas turbine (259) recovers the exhaust heat of the high temperature thermoelectric semiconductor (101), the high temperature thermoelectric semiconductor (101) only needs to have a large (α ² / ρ) or α.

In the combined power generation using the combustion of fossil fuel as a high-temperature heat source, power is also generated via the steam turbine (41) by using the exhaust heat of the power generation via the high-temperature gas turbine (259). Due to the problems of the materials that make up the high temperature gas turbine (259), the limit is approaching high temperatures.
In the present invention, combined power generation is achieved by adding power generation by a thermoelectric semiconductor in front of a high-temperature gas turbine (259). Conventionally, power generation by a thermoelectric semiconductor has been particular to a thermoelectric semiconductor having a large Z. However, in the present invention, a thermoelectric semiconductor having a large (α ² / ρ) or α may be used, so that the selection range of the thermoelectric semiconductor is widened and the feasibility is high.
Thermoelectric semiconductors have no moving parts and are often made of high heat resistance materials. For example, since the melting point of boron carbide (B ₄ C) is 2000 ° C. or higher, the thermal efficiency of thermoelectric semiconductors that generate electricity in the Carnot cycle is markedly improved.
Fusion power generation using deuterium and lithium dissolved in seawater is said to be an eternal energy generator. If uranium dissolved in seawater is extracted as a by-product in the process of extracting deuterium and lithium from seawater, nuclear power generation is considered to be an eternal energy generator.
Radioactivity is an unfavorable property of nuclear power generation, but the world seems to be tolerant of neutrons that are generated in large quantities in fusion power generation. Nuclear power generation is also considered acceptable.

FIG. 1 is a schematic view of generating power through a steam turbine (41) using a conventional ABWR as a high-temperature heat source. FIG. 2 is a schematic diagram of the ABWR according to the present invention, which has been renewed to a combined power generation system that generates power using the thermoelectric semiconductor (100) and that also generates power via the steam turbine (41). FIG. 3 is a schematic diagram of a combined power generation apparatus according to the present invention that generates power also through a steam turbine (41) after generating power with a high-temperature thermoelectric semiconductor (101) using a lead reactor (299) as a high-temperature heat source. FIG. 4 is a schematic diagram of a combined power generation apparatus according to the present invention, which generates power also through a gas turbine (259) after generating power with a high-temperature thermoelectric semiconductor (101) using a lead reactor (299) as a high-temperature heat source.

Explanation of symbols

2 is a nuclear fuel assembly.
3 is a control rod.
4 is a control bar extension bar.
5 is a control rod drive.
6 is a rotating wing.
7 is an internal pump motor.
9 is the core plate.
10 is a pressure vessel.
11 is a shroud.
12 is a steam separator.
13 is a dryer.
14 is a gap area.
21 is high-pressure unsaturated water.
22 is a high-pressure two-phase flow.
23 is high-pressure saturated steam.
24 is high-pressure superheated steam.
30 is a water supply booster pump.
31 is a high-pressure steam pipe.
32 is a high-pressure water supply pipe.
41 is a steam turbine.
42 is a generator.
43 is a condenser.
100 is a thermoelectric semiconductor.
101 is a high-temperature thermoelectric semiconductor.
103 is a terminal.
132 is a water supply pipe with a built-in thermoelectric semiconductor.
201 is a low-pressure heat-resistant container.
202 is a partition wall.
203 is a heat shielding board.
204 is low-pressure gas.
205 is low-pressure low-temperature molten lead.
206 is low pressure high temperature molten lead.
207 is an upper lattice plate.
208 is the top lid.
209 is a joint.
211 is an upper control rod drive.
223 is a high pressure low temperature water pipe.
224 is a high pressure high temperature steam pipe.
225 is a high-pressure capillary.
230 is a lead feed pump.
231 is a low-pressure lead pipe.
232 is low-pressure high-temperature lead piping.
241 is a low-pressure heat-resistant container 2.
242 is a partition wall 2.
245 is low-pressure low-temperature molten lead 2.
246 is low-pressure high-temperature molten lead 2.
247 is a pressure relief cylinder.
248 is a steam relief valve.
251 is high-pressure high-temperature gas piping.
252 is a high-pressure low-temperature gas supply pipe.
253 is a high pressure low temperature gas pipe.
254 is a high pressure high temperature gas pipe.
258 is a gas compressor.
259 is a gas turbine.
260 is a cooler.
261 is a gas relief valve.
299 is a lead reactor.
399 is a steam generator.
499 is a gas heater.

Claims (3)

  The pressure in the pressure vessel (10) is maintained at the pressure of the conventional ABWR, the internal pump (7), the rotor blade (6), the steam separator (12) and the dryer (13) are deleted, and the core flow rate is reduced to steam. Make the core upper coolant into high-pressure superheated steam (24) with the same flow rate, and pass through the thermoelectric semiconductor built-in water supply pipes (132) branched from the high-pressure water supply pipes (32) through the upper side where the dryer (13) was located. The thermoelectric semiconductor (100) with a melting point of 286 ° C or higher is built in the thermoelectric semiconductor built-in water supply pipe (132) and generated by the thermoelectric semiconductor (100), and then the high-pressure superheated steam (24) The renewed ABWR is characterized in that it is a combined power generation that generates power even through the conventional ABWR steam turbine (41) by the high-pressure saturated steam (23) cooled by the thermoelectric semiconductor built-in water supply pipe (132).   High-temperature melting from lead-type reactor (299) using a lead-type reactor (299) with a nuclear fuel assembly (2) containing MOX in a low-pressure heat-resistant vessel (201) and lead as a coolant as a high-temperature heat source After generating electricity with a high-temperature thermoelectric semiconductor (101) with a melting point of 286 ° C or higher installed in a low-pressure lead pipe (231) connecting a steam generator (399) that generates steam with lead and a lead-type reactor (299), steam A combined power generation apparatus that generates power even through a steam turbine (41) using high-pressure and high-temperature steam generated by a generator (399).   High-temperature melting from lead-type reactor (299) using lead-type reactor (299) that contains nuclear fuel assembly (2) containing MOX in a low-pressure heat-resistant vessel (201) and lead as a coolant as a high-temperature heat source After generating electricity with a high-temperature thermoelectric semiconductor (101) with a melting point of 286 ° C or higher installed in a low-pressure lead pipe (231) that connects a gas heater (499) that raises the gas temperature with lead and a lead-type reactor (299), A combined power generation apparatus that generates power via the gas turbine (259) using the gas heated by the gas temperature riser (499).

Images