CN101916594B - Passive nuclear power station LOCA (Loss of Coolant Accident) accident mitigating system - Google Patents
Passive nuclear power station LOCA (Loss of Coolant Accident) accident mitigating system Download PDFInfo
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- CN101916594B CN101916594B CN201010233036A CN201010233036A CN101916594B CN 101916594 B CN101916594 B CN 101916594B CN 201010233036 A CN201010233036 A CN 201010233036A CN 201010233036 A CN201010233036 A CN 201010233036A CN 101916594 B CN101916594 B CN 101916594B
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention discloses a passive nuclear power station LOCA (Loss of Coolant Accident) accident mitigating system belonging to the technical field of nuclear power station safety. Memory alloy is connected with a four-bar mechanism and a valve in series to form a corresponding memory alloy intelligent switching device by utilizing the characteristic that the memory alloy generates contraction deformation at certain temperature, and the memory alloy intelligent switching device is installed at a proper position in a containment and executes a corresponding brake action under the condition that high-temperature and high-pressure steam is filled in the LOCA accident containment. The strong moisture absorption characteristic of lithium bromide solution is utilized to absorb the high-temperature and high-pressure steam in the containment, thereby achieving the goal of mitigating the accident. Lots of passive modes of natural circulation, four-bar mechanism power transmission, pressure action and the like exist in the system. The system mainly adopts the passive automatic operation and has the advantages of convenient implementation, simple control and high reliability, safety and stability.
Description
Technical field
The invention belongs to the nuclear plant safety technical field, particularly a kind of non-active nuclear power station cut accident mitigation system.Specifically, be because cut accident (LOCA) appears in nuclear power station, cause refrigerant injection in the loop in containment; Cause the containment HTHP and major accident possibly caused the time; Nuclear power station moisture absorption system auto-action utilizes salt solusion, makes it moisture absorption and step-down cooling; Realize suppressing or the alleviation accident, the harmfulness of accident is reduced.
Background technology
When the LOCA accident appearred in pressurized-water reactor nuclear power plant, the water of HTHP can become steam in the loop, and water vapour sprays and goes into containment, causes the rising of the pressure and temperature of containment.If deal with improperly, with the major accident of initiated core power plant.At present in two generation presurized water reactors, main processing mode is, utilizes the normal operation of safety injection system, can realize the inhibition to accident, and can be in the harm that alleviates accident to a certain degree.Existing safety injection system mainly contains high pressure, middle pressure and three types of safety injection systems of low pressure.Wherein removing middle pressure safety injection system is that depended on pressure triggers, belong to non-active outside, high pressure and low pressure safety injection system all lean on the power drive of signal triggering water pump to turn round.In the design of advanced reactor, adopting reliable non-passive safety measure then is an important sign.Adopted non-passive safety shell cooling system PCS like AP1000, utilized gravity drainage and natural convection air to realize steam cooled in the steel containment vessel and step-down.But no matter be the active system of two generations heap employing, the passive system that still adopts with AP1000, main implementation all is to be realized the principle of step-down simultaneously by the cooling beginning.Solve more effectively step-down cooling under accident conditions, from the purpose of decompression beginning, just must the novel passive system of design.This system must directly handle the variation that accident conditions presses down the field of force and temperature field, and directly triggering system apace with effective alleviation accident, guarantees the safety of nuclear power station and even surrounding environment.
Summary of the invention
The objective of the invention is to the deficiency of prior art and propose a kind of non-active nuclear power station cut accident mitigation system; It is characterized in that this cut accident mitigation system is that a kind of moisture absorbing of salt solusion that utilizes is realized the system to the decrease temperature and pressure in the nuclear power plant containment shell; Specifically be to utilize the strong moisture absorbing of lithium-bromide solution to realize to coming the system of decrease temperature and pressure in the npp safety shell; At containment 18 internal upper parts; First group of memorial alloy intelligent switch device A connects the case lid of lithium-bromide solution case 1; First group of memorial alloy intelligent switch device A is the valve that is connected into one group of non-active switch or employing pressure automatic switch by temperature control memorial alloy and corresponding valve as the valve of opening case lid; Second group of memorial alloy intelligent switch device B is installed in the top of lithium-bromide solution case 1, and one of which end supply pipe inserts the last space of lithium-bromide solution case 1, lithium-bromide solution filler casing 11 connections that the other end and containment are outside; The 3rd group of memorial alloy intelligent switch device C is installed in the side of leaning on the bottom of lithium-bromide solution case 1; And be connected overflow passage 14 parallel connections on lithium-bromide solution case 1 top, the water inlet pipe and water outlet pipe of heat interchanger 13 is connected to the top of lithium-bromide solution case 1 and leans on the side of bottom; Bottom in containment 18, pressure vessel 15 is formed series loop with steam generator 16, voltage stabilizer 17; Increased its moisture absorption efficient like this.
Pressure loading valve 5 also is installed on the case lid of said lithium-bromide solution case 1, is used as the standby valve under first group of memorial alloy intelligent switch failure conditions.
Last space in the said lithium-bromide solution case is an air, and the lithium-bromide solution of half chests has been adorned in following space.
Lithium-bromide solution filler casing 11 provides certain density lithium-bromide solution; Because the containment outside is a normal temperature and pressure; The mass concentration of lithium-bromide solution should not surpass 66% under this condition, otherwise when solution temperature reduces, will have crystallization to separate out, and concentration is lithium-bromide solution moisture sorption effect the best of 66% under the normal temperature and pressure; So lithium-bromide solution can maintain a constant relatively concentration level, the process of effectively alleviation accident in the containment under accident conditions; The lithium-bromide solution case also is connected with heat interchanger, and lithium-bromide solution is walked shell side, and chilled water is walked tube side; Carry out heat exchange; Because lithium-bromide solution concentration will be thinning gradually in moisture absorption process constantly, temperature also raises gradually, thus the density of causing and temperature difference; Produce Natural Circulation, reach a kind of non-active heat exchange effect.
Said lithium-bromide solution is contained in the containment internal box, and its chemical property is stable, not perishable difficult decomposition in atmosphere.Have strong hydroscopicity, and the concentration of saturated lithium bromide water solution reaches 60% at normal temperatures, concentration is big more, and temperature is low more, and wettability power is strong more, and coefficient of heat conductivity increases with the rising of temperature, is a kind of efficient water vapor absorbing agent and air humidity conditioning agent.Under the LOCA accident conditions, can absorb in a large number and riddle high-temperature high-pressure steam in the containment, thereby effectively reduce containment internal pressure, temperature and humidity.
Said memorial alloy intelligent switch device A, B, C-structure are the same, are made up of memorial alloy 2, four-bar mechanism 3 and valve 4; Said memorial alloy is a temperature-sensing element (device); Adopt the four-bar mechanism mechanical connection between memorial alloy 2 and the valve; Thereby reach a kind of non-active control effect; Be installed in position suitable in the containment, in LOCA accident containment, be full of under the situation of high-temperature high-pressure steam, carry out corresponding braking maneuver.
Said four-bar mechanism is on the horizon bar 3.1 of right angle, flexible connection and vertical bar 3.2; Memorial alloy 2 is respectively through waling stripe 2.1 and vertically bar 3.2 flexible connections; Flexibly connect through vertical connecting rod 2.2 and horizon bar 3.1; Between the other end of horizon bar 3.1 and vertical bar 3.2, flexibly connect stock 3.3 and quarter butt 3.4, form the non-rectangle four-bar mechanism, valve 4 is connected on the tie point of quarter butt 3.4 and horizon bar 3.1.
The present invention compared with prior art; Have following outstanding advantage and effect: the invention provides a kind of non-active nuclear power station LOCA accident mitigation system, is that a kind of switching of memorial alloy by-pass valve control or pressure valve of utilizing realized the system that nuclear plant severe accident is alleviated.It mainly is the switching that comes by-pass valve control through metal at the memory characteristic under the different temperatures.Memorial alloy and respective valves are formed one four bar driving mechanism, and the memorial alloy drawdown deformation of being heated drives valve open, thereby opens the salt solusion case lid when temperature raises, realizes utilizing the lithium-bromide solution moisture absorption to reduce pressure; On the feed pipeline, be provided with this memorial alloy intelligent switch system too, the drawdown deformation with the rising of temperature of its memorial alloy impels the aperture of feed valve to increase, and more salt solusion gets into the salt solusion case; And memorial alloy intelligent switch systemic effect is just in time opposite on the discharge line, and its contraction can cause valve opening to reduce, and discharges the salt solusion case thereby suppress salt solusion.When temperature was low, alloy recovered former remember condition, drove valve by four-bar mechanism and carried out above-mentioned opposite action.This system can also start by depended on pressure simultaneously, to satisfy the desired multifarious Safety Design principle of npp safety criterion.Native system is directly responded to and the most direct parameter--the variation of temperature of core power variation, and the power transmission characteristic of the Telescopic of memorial alloy and four-bar mechanism can make equipment operation steady in a long-term, dependable performance.This device can be under various pressure conditions uses effectively, and the harm that suppresses or slow down the coolant loss accident is had positive effect.Can be easier to carry out the marketization and be applicable, should be one of important technology of the advanced reactor of development.This device control structure is highly sensitive, simple and reliable for structure, has non-active characteristics.
Description of drawings
The nuclear power station LOCA accident mitigation system schematic that Fig. 1 right and wrong are active.
The active memorial alloy intelligent switch device of Fig. 2 right and wrong synoptic diagram.
Embodiment
A kind of non-active nuclear power station LOCA accident mitigation system that The present invention be directed to the deficiency of prior art and provide.Be utilize that the strong moisture absorbing of lithium-bromide solution develops a kind of simple in structure, stable performance, accident mitigation system that reliability is high.Below in conjunction with accompanying drawing concrete structure of the present invention, the course of work and preferred forms are described further.
The nuclear power station LOCA accident mitigation system schematic that Fig. 1 right and wrong are active.The active memorial alloy intelligent switch device of Fig. 2 right and wrong synoptic diagram.Among the figure; At containment 18 internal upper parts; First group of memorial alloy intelligent switch device A connects the case lid of lithium-bromide solution case 1; First group of memorial alloy intelligent switch device A is the valve that is connected into one group of non-active switch or employing pressure automatic switch by temperature control memorial alloy and corresponding valve as the valve of opening case lid; Second group of memorial alloy intelligent switch device B is installed in the top of lithium-bromide solution case 1; And one of which end supply pipe inserts the last space of lithium-bromide solution case 1; The outside lithium-bromide solution filler casing 11 of the other end and containment is communicated with; Second group of memorial alloy intelligent switch device, the supply of control lithium-bromide solution; The 3rd group of memorial alloy intelligent switch device C is installed in the side of leaning on the bottom of lithium-bromide solution case 1; And be connected overflow passage 14 parallel connections on lithium-bromide solution case 1 top, the water inlet pipe and water outlet pipe of heat interchanger 13 is connected to the top of lithium-bromide solution case 1 and leans on the side of bottom; Bottom in containment 18, pressure vessel 15 is formed series loop with steam generator 16, voltage stabilizer 17; Increased its moisture absorption efficient like this.
Pressure loading valve 5 also is installed on the case lid of lithium-bromide solution case 1, is used as the standby valve under first group of memorial alloy intelligent switch failure conditions.
Last space in the said lithium-bromide solution case is an air, and the lithium-bromide solution of half chests has been adorned in following space.
It is 66% lithium-bromide solution that lithium-bromide solution filler casing 11 provides volume by volume concentration, to replenish the lithium-bromide solution in the case in the containment; The lithium-bromide solution case also is connected with heat interchanger, and lithium-bromide solution is walked shell side, and chilled water is walked tube side; Carry out heat exchange; Because lithium-bromide solution concentration will be thinning gradually in moisture absorption process constantly, temperature also raises gradually, thus the density of causing and temperature difference; Produce Natural Circulation, reach a kind of non-active heat exchange effect.
Said lithium-bromide solution is contained in the containment internal box, and its chemical property is stable, not perishable difficult decomposition in atmosphere.Have strong hydroscopicity, and the concentration of saturated lithium bromide water solution reaches 60% at normal temperatures, concentration is big more, and temperature is low more, and wettability power is strong more, and coefficient of heat conductivity increases with the rising of temperature, is a kind of efficient water vapor absorbing agent and air humidity conditioning agent.Under the LOCA accident conditions, can absorb in a large number and riddle high-temperature high-pressure steam in the containment, thereby effectively reduce containment internal pressure, temperature and humidity.
Said memorial alloy intelligent switch device A, B, C-structure are the same, are made up of memorial alloy 2, four-bar mechanism 3 and valve 4; Said memorial alloy is a temperature-sensing element (device), and memorial alloy shrinks with temperature sense or expands, and the four-bar mechanism that passes through to be connected is realized the running control to valve indirectly, is a kind of non-active mode.It is the critical component of the non-active LOCA accident mitigation of temperature induction type system, and can be processed into the size of spring and all kinds of shape and different sizes according to need of work.
Adopt the four-bar mechanism mechanical connection between memorial alloy 2 and the valve, thereby reach a kind of non-active control effect, be installed in position suitable in the containment, in LOCA accident containment, be full of under the situation of high-temperature high-pressure steam, carry out corresponding braking maneuver.Four-bar mechanism as shown in Figure 2 is on the horizon bar 3.1 of right angle, flexible connection and vertical bar 3.2; Memorial alloy 2 is respectively through waling stripe 2.1 and vertically bar 3.2 flexible connections; Flexibly connect through vertical connecting rod 2.2 and horizon bar 3.1; Between the other end of horizon bar 3.1 and vertical bar 3.2, flexibly connect stock 3.3 and quarter butt 3.4, form the non-rectangle four-bar mechanism, valve 4 is connected on the tie point of quarter butt 3.4 and horizon bar 3.1.
System is made up of lithium-bromide solution case, memorial alloy, valve, heat interchanger, water tank and corresponding pipeline; When taking place nuclear power station cooling agent forfeiture design basis accident also down to the initiation major accident; Temperature rises in the containment because refrigerant injection in the containment space, causes.Memorial alloy drives four-bar mechanism and opens valve or case lid owing to the rising of temperature is shunk, and water vapor is absorbed by the lithium-bromide solution in the case thus, reaches and reduces the reactor core pressure and temperature, alleviates the purpose of reactor accident.
The practical implementation process is following: when the LOCA accident appears in presurized water reactor; Cooling medium spurts and causes temperature and humidity rising in the containment; Memorial alloy 2 is out of shape and through four-bar mechanism 3 valve 4 is opened; Lithium-bromide solution case case lid is opened, and water vapor contacts with lithium-bromide solution, and the lithium-bromide solution with wettability power absorbs.Under memorial alloy intelligent switch failure conditions, temperature and pressure can continue to rise, and when arriving certain numerical value, the pressure loading valve 5 that is connected with case lid can be opened immediately, opens thereby also can bromizate lithium liquor box case lid.Memorial alloy 5 distortion simultaneously make valve 7 open; The lithium-bromide solution that proportioning in the stuffing box 11 is good (generally surpassing 66%) is injected in the interior lithium-bromide solution case 1 of containment; Valve 4 and 7 aperture are directly proportional with temperature, and promptly temperature is high more, and the case lid aperture is big more; The contact area of water vapor and lithium-bromide solution is big more, and the moisture absorption cooling-down effect is good more; Along with the rising of temperature, the flow of filler pipeline is also big more, injects also corresponding the increasing of lithium-bromide solution of salt solusion water tank 1.The aperture of valve 10 then is inversely proportional to temperature, and temperature is high more, and its aperture is more little, and the lithium-bromide solution that spills out is few more, and when temperature increased, the solution in the lithium-bromide solution water tank 1 increased like this, and the wettability power of total system is enhanced naturally.When the lithium-bromide solution amount is increased to the run-down pipe height in the lithium-bromide solution water tank 1, lithium-bromide solution will guarantee that the lithium-bromide solution in the casing can not diffuse out in the containment through overflow passage row to liquid waste treatment system.When whole process is carried out; Chilled water in lithium-bromide solution in the lithium-bromide solution water tank 1 and the heat interchanger 13 is owing to exist density difference and temperature difference; Meet the Natural Circulation condition; Thereby can be spontaneous carry out exchange heat, thereby guaranteed that also the lithium-bromide solution in the casing 1 remains on a relative stationary temperature; The inner lithium-bromide solution case of containment links to each other with the heat interchanger of outside since at lithium-bromide solution in continuous moisture absorption process, density and temperature can reduce gradually, thereby can realize the heat exchange to containment inside lithium-bromide solution through the mode of Natural Circulation.
With regard to Fig. 1 and Fig. 2, when reactor generation coolant loss accident, because coolant temperature sharply raises in the containment; Cause the containment temperature to raise; Memorial alloy receives the influence that temperature raises, drive four-bar mechanism and open valve thereby can shrink, under the lithium-bromide solution case in the space in lithium-bromide solution will absorb the water vapour of LOCA accident generation; Play the effect of containment being fallen wet, step-down and cooling, the development of alleviation accident thus.Non-active nuclear power station LOCA accident mitigation system can change according to temperature variation or pressure and start; And be designed to realize easily the various apertures of valve according to the ratio of gear of the shrinkage factor of memorial alloy and four-bar mechanism; Thereby reach all kinds of flows, so that realize alleviation and control targetedly effectively to accident.
Core substance lithium-bromide solution of the present invention, its chemical property is stable, not perishable difficult decomposition in atmosphere; Its boiling point has strong hydroscopicity up to 1265 ℃, and concentration is big more; Temperature is low more; Wettability power is strong more, and coefficient of heat conductivity increases with the rising of temperature, is a kind of efficient water vapor absorbing agent and air humidity conditioning agent.Under the LOCA accident conditions, can absorb in a large number and riddle high-temperature high-pressure steam in the containment, thereby effectively reduce containment internal pressure, temperature and humidity.
Critical component memory alloy material of the present invention is generally selected copper, titanium or nickel alloy for use.It has shape memory function, and characteristics such as wear-resistant, anticorrosive, high damping and super-elasticity are arranged.Its fusing point to prevent its fusing, is lost its function up to 1700 ℃.Be a kind of outstanding functional material, can satisfy its practical applications demand.
Said lithium-bromide solution is contained in the containment internal box, and its chemical property is stable, not perishable difficult decomposition in atmosphere.Have strong hydroscopicity, and the concentration of saturated lithium bromide water solution reaches 60% at normal temperatures, concentration is big more, and temperature is low more, and wettability power is strong more, and coefficient of heat conductivity increases with the rising of temperature, is a kind of efficient water vapor absorbing agent and air humidity conditioning agent.Under the LOCA accident conditions, can absorb in a large number and riddle high-temperature high-pressure steam in the containment, thereby effectively reduce containment internal pressure, temperature and humidity.
Claims (8)
1. a non-active nuclear power station cut accident mitigation system is characterized in that, this cut accident mitigation system is that a kind of moisture absorbing of salt solusion that utilizes is realized the system to the decrease temperature and pressure in the nuclear power plant containment shell; At containment (18) internal upper part; First group of memorial alloy intelligent switch device (A) connects the case lid of lithium-bromide solution case (1); First group of memorial alloy intelligent switch device (A) is the valve that is connected into one group of non-active switch by temperature control memorial alloy and corresponding valve as the valve of opening case lid; Second group of memorial alloy intelligent switch device (B) is installed in the top of lithium-bromide solution case (1), and one of which end supply pipe inserts the last space of lithium-bromide solution case (1), lithium-bromide solution filler casing (11) connection that the other end and containment are outside; The 3rd group of memorial alloy intelligent switch device (C) is installed in the side of leaning on the bottom of lithium-bromide solution case (1); And be connected overflow passage (14) parallel connection on lithium-bromide solution case (1) top, the water inlet pipe and water outlet pipe of heat interchanger (13) is connected to the top of lithium-bromide solution case (1) and leans on the side of bottom; Bottom in containment (18), pressure vessel (15) and steam generator (16), voltage stabilizer (17) are formed series loop; Increased moisture absorption efficient like this.
2. according to the said non-active nuclear power station cut accident mitigation system of claim 1; It is characterized in that; Pressure loading valve (5) also is installed on the case lid of said lithium-bromide solution case (1), is used as the standby valve under first group of memorial alloy intelligent switch failure conditions.
3. according to the said non-active nuclear power station cut accident mitigation system of claim 1, it is characterized in that the last space in the said lithium-bromide solution case is an air, the lithium-bromide solution of half chests has been adorned in following space.
4. according to the said non-active nuclear power station cut accident mitigation system of claim 1, it is characterized in that it is 66% lithium-bromide solution that lithium-bromide solution filler casing (11) provides volume by volume concentration, to replenish the lithium-bromide solution in the case in the containment; Lithium-bromide solution case (1) also is connected with heat interchanger (13), and lithium-bromide solution is walked shell side, and chilled water is walked tube side; Carry out heat exchange; Because lithium-bromide solution concentration will be thinning gradually in moisture absorption process constantly, temperature also raises gradually, thus the density of causing and temperature difference; Produce Natural Circulation, reach a kind of non-active heat exchange effect.
5. according to the said non-active nuclear power station cut accident mitigation system of claim 1, it is characterized in that said lithium-bromide solution is contained in the containment internal box; Its chemical property is stable, and not perishable difficult decomposition has strong hydroscopicity in atmosphere; And the volume by volume concentration of saturated lithium bromide water solution reaches more than 60% at normal temperatures, and concentration is big more; Temperature is low more; Wettability power is strong more, and coefficient of heat conductivity increases with the rising of temperature, is a kind of efficient water vapor absorbing agent and air humidity conditioning agent; Under the LOCA accident conditions, can absorb in a large number and riddle high-temperature high-pressure steam in the containment, thereby effectively reduce containment internal pressure, temperature and humidity; The inner lithium-bromide solution case of containment links to each other with the heat interchanger of outside since at lithium-bromide solution in continuous moisture absorption process, density and temperature can reduce gradually, thereby can realize the heat exchange to containment inside lithium-bromide solution through the mode of Natural Circulation.
6. according to the said non-active nuclear power station cut accident mitigation system of claim 1, it is characterized in that said three groups of memorial alloy intelligent switch devices (A, B, C) structure is the same, form by memorial alloy (2), four-bar mechanism (3) and valve (4); Said memorial alloy is a temperature-sensing element (device); Adopt the four-bar mechanism mechanical connection between memorial alloy (2) and the valve; Thereby reach a kind of non-active control effect; Be installed in position suitable in the containment, in LOCA accident containment, be full of under the situation of high-temperature high-pressure steam, carry out corresponding braking maneuver.
7. according to the said non-active nuclear power station cut accident mitigation system of claim 6; It is characterized in that; Said four-bar mechanism is on horizon bar of right angle, flexible connection (3.1) and vertical bar (3.2); Memorial alloy (2) through waling stripe (2.1) and vertically bar (3.2) flexible connection, flexibly connects through vertical connecting rod (2.2) and horizon bar (3.1) respectively, between the other end of horizon bar (3.1) and vertical bar (3.2), flexibly connects stock (3.3) and quarter butt (3.4); Form the non-rectangle four-bar mechanism, valve (4) is connected quarter butt
(3.4) and on the tie point of horizon bar (3.1).
8. according to the said non-active nuclear power station cut accident mitigation system of claim 1, it is characterized in that said first group of memorial alloy intelligent switch device (A) also adopts the pressure automatic switch valve as the valve of opening case lid.
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| CN201010233036A CN101916594B (en) | 2010-07-16 | 2010-07-16 | Passive nuclear power station LOCA (Loss of Coolant Accident) accident mitigating system |
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| CN201010233036A CN101916594B (en) | 2010-07-16 | 2010-07-16 | Passive nuclear power station LOCA (Loss of Coolant Accident) accident mitigating system |
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| CN106409355B (en) * | 2016-10-09 | 2021-09-17 | 中国核电工程有限公司 | Passive automatic control system for starting containment cooling system |
| CN107393613A (en) * | 2017-07-31 | 2017-11-24 | 江苏华洋新思路能源装备股份有限公司 | The passive butterfly overflow cover of material-changing water tank built in nuclear power generating sets containment |
| CN110444301B (en) * | 2019-08-13 | 2022-07-01 | 中国核动力研究设计院 | Experimental device and experimental method for simulating supercritical pressure transient working condition |
| CN111798999B (en) * | 2020-06-04 | 2021-11-09 | 江苏核电有限公司 | Method for reducing switch failure rate of electric heater of voltage stabilizer in nuclear power plant |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1990016071A1 (en) * | 1988-05-09 | 1990-12-27 | Siemens Aktiengesellschaft | Nuclear power station with a safety shell and pressure-relieving process |
| US20080137796A1 (en) * | 2005-12-06 | 2008-06-12 | General Electric Company | Method for reducing carbon steel corrosion in high temperature, high pressure water |
| CN101477842A (en) * | 2009-01-13 | 2009-07-08 | 华北电力大学 | Steam pressure tablet, thin-film and metal mesh type nuclear plant severe accident relieving apparatus |
| CN101777392A (en) * | 2009-11-17 | 2010-07-14 | 华北电力大学 | Accident buffering and removing device for nuclear power station by supercritical CO2 |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS54114695A (en) * | 1978-02-27 | 1979-09-06 | Toshiba Corp | Pressure suppressor |
| JP2915012B2 (en) * | 1989-08-30 | 1999-07-05 | 株式会社日立製作所 | Nuclear power plant |
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Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO1990016071A1 (en) * | 1988-05-09 | 1990-12-27 | Siemens Aktiengesellschaft | Nuclear power station with a safety shell and pressure-relieving process |
| US20080137796A1 (en) * | 2005-12-06 | 2008-06-12 | General Electric Company | Method for reducing carbon steel corrosion in high temperature, high pressure water |
| CN101477842A (en) * | 2009-01-13 | 2009-07-08 | 华北电力大学 | Steam pressure tablet, thin-film and metal mesh type nuclear plant severe accident relieving apparatus |
| CN101777392A (en) * | 2009-11-17 | 2010-07-14 | 华北电力大学 | Accident buffering and removing device for nuclear power station by supercritical CO2 |
Non-Patent Citations (2)
| Title |
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| JP平3-85493A 1991.04.10 |
| JP昭54-114695A 1979.09.06 |
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