CN103390436A - Integral reactor passive reactor cavity runner system and application method thereof - Google Patents

Integral reactor passive reactor cavity runner system and application method thereof Download PDF

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CN103390436A
CN103390436A CN2013103221887A CN201310322188A CN103390436A CN 103390436 A CN103390436 A CN 103390436A CN 2013103221887 A CN2013103221887 A CN 2013103221887A CN 201310322188 A CN201310322188 A CN 201310322188A CN 103390436 A CN103390436 A CN 103390436A
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reactor
cavity
runner
pit
integral
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CN103390436B (en
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秦忠
宋丹戎
李庆
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Nuclear Power Institute of China
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Nuclear Power Institute of China
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    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract

The invention discloses an integral reactor passive reactor cavity runner system and an application method thereof. The integral reactor passive reactor cavity runner system comprises a reactor cavity and a reactor pit as well as an annular main shield wall positioned between the reactor cavity and the reactor pit, wherein the reactor pit is formed below the main shield wall, and the reactor cavity is positioned above the main shield wall; the reactor cavity and the reactor pit are communicated through an L-type runner; one end, close to a reactor pit, of the runner is provided with a wind shield, and the top of the reactor cavity is provided with two gas releasing holes. The integral reactor passive reactor cavity runner system and the application method thereof provided by the invention have the advantages that a passive reactor cavity runner structure can submerge the reactor cavity and the reactor pit of an integral reactor in a passive manner, cool a reactor pressure vessel, maintain the integrity of the reactor pressure vessel, prevent the reactor pressure vessel from being melted out through a reactor core melt, provide the injection flow for cooling a reactor core of the reactor for a long time, and prevent risks of the overpressure and hydrogen gathering explosive of the reactor cavity of the integral reactor.

Description

The non-active heap of integral reactor chamber flow passage system and application process
Technical field
The present invention relates to integral reactor, integral reactor has high security as a kind of innovation heap type, for the nuclear energy multi-usage, has created condition, can be used for nuclear energy power generation, the heat supply of nuclear energy urban area, the heat supply of nuclear power industry technique and nuclear desalination etc.The invention provides the non-active heap of a kind of integral reactor chamber flow passage structure scheme,, as the part of engineered safeguards features, can be after the LOCA accident take non-enabling fashion and realize that the heap chamber floods the cooled reactor pressure vessel and water flow passage is provided, release channel is provided, prevents that hydrogen from gathering blast effective hydrogen diffusion runner is provided after major accident as diffusion of vapor.
Background technology
After reactor generation loss of-coolant accident (LOCA), a large amount of mass-energy is released in containment, causes that containment compartment temperature and pressure raise rapidly., for the cooled reactor pressure vessel, prevent each technique compartment superpressure, and prevent that hydrogen from gathering the generation blast, must arrange rational runner.
Conventional loop-type PWR nuclear power plant is provided with the major loop plant compartment and directly leads to containment hall free space, for each compartment air pressure balance after the LOCA accident, prevent that hydrogen from gathering and produce blast release way and the space of dissolving preferably are provided.Integral reactor is without the major loop plant compartment, and reactor cavity and reactor pit relative closure, certainly exist heap chamber superpressure and hydrogen and gather the danger of blast after the LOCA accident.The whole world is at present in-service to be reached at the PWR nuclear power plant of building all without the referential non-active heap of integral reactor chamber flow passage structure scheme.
Summary of the invention
The object of the present invention is to provide the non-active heap of a kind of integral reactor chamber flow passage system and application process, can prevent each technique compartment superpressure, and prevent that hydrogen from gathering the generation blast, must arrange rational runner.
Implementation of the present invention is as follows: the non-active heap of integral reactor chamber flow passage system, comprise reactor cavity and reactor pit, and the annular main shield wall between reactor cavity and reactor pit, reactor pit is positioned at main shield wall below, and reactor cavity is positioned at main shield wall top; Reactor cavity and reactor pit are communicated with by runner, and runner is provided with deep bead near an end of reactor pit, and the reactor cavity top has the air release hole.
Runner of the present invention is communicated with the cooling water source of the built-in material-changing water tank of reactor building, when imaginary LOCA loss of-coolant accident (LOCA) occurs when, the water of built-in material-changing water tank flows to reactor pit by the L-type runner after relying on gravity piii reactor chamber again, current flood reactor pit, reactor cavity successively, the cooled reactor pressure vessel.After built-in material-changing water tank and reactor cavity flood water level balance, built-in material-changing water tank gravity water filling automatic stop.After not had by water logging in reactor pit, chilled water contacts with reactor pressure vessel and can produce a large amount of steam, and steam and hydrogen that these steam and loss of-coolant accident (LOCA) produce are gathered in reactor cavity in a large number, cause reactor cavity pressure and temperature sharply to rise.These steam and hydrogen diffuse to reactor hall by the air release hole under the air pressure self-poise drives, non-kinetic energy hydrogen recombiner can be before the hydrogen that after major accident, reactor is released into reactor cavity diffusing to the containment hall high efficiency composition nearby.Pressure in reactor cavity and reactor pit reduces like this, and the reduction of internal hydrogen concentration, the threat of can not blasting.And existing integral reactor is without the major loop plant compartment, and reactor cavity and reactor pit relative closure certainly exist heap chamber superpressure and hydrogen and gather the danger of blast after the LOCA accident.Comparatively speaking, security performance of the present invention improves greatly.
And when normal operation, in order to eliminate the ventilation volume by-pass flow of reactor pit, abundant cooled reactor reactor pit and reactor cavity, runner exit is provided with deep bead.During reactor operation, deep bead is closed runner automatically under Action of Wind pressure in reactor pit.Automatically open runner under the effect of water gravity head after the LOCA accident in runner.
General, the preferred cooling water source of the present invention is built-in water source, i.e. and the present invention also comprises built-in material-changing water tank, and described built-in material-changing water tank is connected with reactor cavity by isolation valve.
For preventing that foreign matter and chip from stopping up runner, is provided with the grid filter screen on the path of runner.
Preferably, need to carry out resistant to elevated temperatures filter screen, so the grid filter screen is steel aperture plate lattice structure.
The air release hole is communicated with the containment hall.Be provided with non-kinetic energy hydrogen recombiner in top, air release hole or air release hole.Non-kinetic energy hydrogen recombiner can, at the hydrogen that after major accident, reactor is released into reactor cavity high efficiency composition nearby before diffusion, can make the gas density of hydrogen that is released into the containment hall in safety limit.
Preferably, described runner is L shaped runner.
The end that runner is communicated with reactor cavity is positioned at the reactor cavity minimum point.
The application process of the non-active heap of integral reactor chamber flow passage system, when imaginary loss of-coolant accident (LOCA) occurs, comprise following step of carrying out successively,
Step 1: start reactor high pressure and middle pressure safety injection system;
Step 2: after question response heap high pressure and middle pressure peace were annotated and completed, isolation valve was opened, and the water of built-in material-changing water tank flows to reactor pit by runner after relying on gravity piii reactor chamber again, and current flood reactor pit, reactor cavity successively;
Step 3: wait for, after built-in material-changing water tank and reactor cavity water level balance, built-in material-changing water tank gravity water filling automatic stop;
Step 4: when carry out step 2, open non-active hydrogen recombiner, reactor cavity internal cause loss of-coolant accident (LOCA) and cooled reactor pressure vessel and the steam that produces and hydrogen diffuse to reactor hall by the air release hole under air pressure balance drives, non-kinetic energy hydrogen recombiner can be before the hydrogen that after major accident, reactor is released into reactor cavity diffusing to the containment hall high efficiency composition nearby.
When the LOCA accident occurs when, after isolation valve is opened, built-in material-changing water tank by gravity with water piii reactor chamber after, current flow to reactor pit by the L-type runner again, therefore, can, by gravity, with non-enabling fashion realization response heap chamber and reactor pit, flood.
For preventing that foreign matter and chip from stopping up runner, L-type runner entrance is provided with steel grid filter screen.For eliminating the by-pass flow of reactor pit ventilation volume, the L-type runner exit is provided with deep bead.During reactor operation, L-type runner deep bead is closed the L-type runner under Action of Wind pressure in reactor pit, automatically opens runner under the effect of water gravity head after the LOCA accident in the L-type runner.
Have a plurality of steam on circular or square reactor cavity ceiling and the hydrogen release aperture is directly led to the containment hall.Be provided with non-active hydrogen recombiner on reactor cavity steam and hydrogen release aperture, can be at the hydrogen that after major accident, reactor is discharged high efficiency composition nearby before diffusion.
The invention has the advantages that: non-active heap chamber flow passage structure can be after integrated reacting piles up the LOCA accident and floods reactor cavity and reactor pit with non-enabling fashion, the cooled reactor pressure vessel, keep the integrality of reactor pressure vessel, prevent that reactor pressure vessel is by reactor core fused mass burn through, for the long-term cooling injection flow that provides of reactor core, and can eliminate integral reactor heap chamber superpressure and hydrogen and gather the risk of blast.
Description of drawings
Fig. 1 is plan structure schematic diagram of the present invention.
Fig. 2 is side-looking structural representation of the present invention.
Reference numeral in figure is expressed as respectively: 1, built-in material-changing water tank; 2, isolation valve; 3, reactor cavity; 4, L-type runner; 5, reactor pit; 6, steel grid filter screen; 7, deep bead; 8, air release hole; 9, non-kinetic energy hydrogen recombiner; 10, containment hall.
Embodiment
Embodiment one
As shown in Figure 1, 2.
The non-active heap of integral reactor chamber flow passage system, comprise reactor cavity 3 and reactor pit 5, and the annular main shield wall between reactor cavity 3 and reactor pit 5, reactor pit 5 is positioned at main shield wall below, and reactor cavity 3 is positioned at main shield wall top; Reactor cavity 3 and reactor pit 5 are communicated with by runner 4, and runner 4 is provided with deep bead 7 near an end of reactor pit 5, and reactor cavity 3 tops have air release hole 8, as shown in Figure 2, in main shield wall annular space, reactor pressure vessel are installed.
Traditional reactor does not have runner 4, and runner of the present invention is connected with the cooling water source of the external world or reactor building inside.When having an accident, the interior rapid introducing cooling water source of runner 4 enters reactor pit 5, and after not had by water logging in question response heap reactor pit, steam or hydrogen that it is inner overflow, arrive the reactor cavity 3 of top, can assemble a large amount of steam and hydrogen in this chamber, security performance is on the hazard, at this moment, continue the perfusion chilled water, after chilled water floods reactor pit, and will flood reactor cavity, and make steam and hydrogen in reactor cavity 3 discharge by the air release hole 8 of top.Pressure in reactor cavity and reactor pit 5 reduces like this, and reduces density of hydrogen, can generating steam or hydrogen explosion threat.And existing integral reactor is without the major loop plant compartment, and reactor cavity and reactor pit relative closure certainly exist heap chamber superpressure and hydrogen and gather the danger of blast after the LOCA accident.Comparatively speaking, security performance of the present invention improves greatly.
And when normal operation, in order to eliminate the ventilation volume by-pass flow of reactor pit, abundant cooled reactor reactor pit 5 and reactor cavity 3, runner 4 outlets are provided with deep bead 7.During reactor operation, deep bead 7 is closed runner 4 automatically under the interior Action of Wind pressure of reactor pit 5.Automatically open runner after the LOCA accident under the effect of the interior water gravity head of runner 4.The LOCA accident is unexpected loss of-coolant accident (LOCA).
General, built-in water source in the preferred cooling water source of the present invention, i.e. the present invention also comprises built-in material-changing water tank 1, described built-in material-changing water tank 1 is communicated with reactor cavity 3 by isolation valve.
For preventing that foreign matter and chip from stopping up runner, is provided with grid filter screen 6 on the path of runner 4.
Preferably, need to carry out resistant to elevated temperatures filter screen, so grid filter screen 6 is steel aperture plate lattice structure.
8 tops, air release hole are provided with non-kinetic energy hydrogen recombiner 9.Non-kinetic energy hydrogen recombiner 9 can be at the hydrogen that after major accident, reactor is discharged high efficiency composition nearby before diffusion.
Air release hole 8 is communicated with containment hall 10.Arrive the interior gas density of hydrogen in containment hall 10 in safety limit.
Preferably, described runner 4 is L shaped runner.
The end that runner 4 is communicated with reactor cavity 3 is positioned at reactor cavity 3 minimum points.
The application process of the non-active heap of integral reactor chamber flow passage system, while meeting accident loss of-coolant accident (LOCA), comprise following step of carrying out successively,
Step 1: start reactor high pressure and middle pressure safety injection system;
Step 2: after question response heap high pressure and middle pressure peace were annotated and completed, isolation valve was opened, and the water of built-in material-changing water tank flows to reactor pit by the L-type runner after relying on gravity piii reactor chamber again, and current flood reactor pit, reactor cavity successively;
Step 3: wait for, after built-in material-changing water tank and reactor cavity water level balance, built-in material-changing water tank gravity water filling automatic stop;
Step 4: reactor cavity internal cause loss of-coolant accident (LOCA) and cooled reactor pressure vessel and the steam that produces and hydrogen diffuse to reactor hall by the air release hole under air pressure balance drives, non-kinetic energy hydrogen recombiner can be before the hydrogen that after major accident, reactor is released into reactor cavity diffusing to the containment hall high efficiency composition nearby.
Embodiment two
As shown in Figure 1, 2.
The non-active heap of integral reactor of the present invention chamber flow passage system, comprise that isolation valve 2, L-type runner, circle or square reactor cavity 3, circle or square reactor pit 5, air release hole 8 reactor cavity areas are about 150m 2, head room is about 6m.
When the LOCA accident occurred, reactor cavity was full of a large amount of steam,, along with after annotating to reactor high pressure and middle pressure peace and completing, opened isolation valve 2, and the water loading amount is about 1200m 3Built-in material-changing water tank 1 by gravity with water piii reactor heap chamber 3 after, the runner 4 that current are 400mm * 400mm by 2 flow areas again flows to reactor pit 5.Along with the gathering of volume of water input, flood water level and raise gradually, flood gradually reactor pit and reactor cavity, finally with non-enabling fashion realization response heap chamber 3 and reactor pit 5, flood.
For preventing that foreign matter and chip from stopping up runner, runner 4 entrances are provided with and highly are the grid filter screen 6 of 800mm.For eliminating the by-pass flow of reactor pit ventilation volume, abundant cooled reactor reactor pit 5 and reactor cavity 3, runner 4 outlets are provided with deep bead 7.During reactor operation, deep bead 7 is closed runner 4 automatically under the interior Action of Wind pressure of reactor pit 5.Automatically open runner after the LOCA accident under the effect of the interior water gravity head of runner 4.
Have 4 square air release holes 8 on square reactor cavity 3 ceilings and directly lead to containment hall 10.Air release hole bore size is 1300mm * 1300mm.Be provided with a non-active hydrogen recombiner 9 on each air release hole 8, can be at the hydrogen that after major accident, reactor is discharged high efficiency composition nearby before diffusion.
As mentioned above, can well realize the present invention.

Claims (9)

1. the non-active heap of integral reactor chamber flow passage system, it is characterized in that: comprise reactor cavity (3) and reactor pit (5), and be positioned at annular main shield wall between reactor cavity (3) and reactor pit (5), reactor pit (5) is positioned at main shield wall below, and reactor cavity (3) is positioned at main shield wall top; Reactor cavity (3) and reactor pit (5) are communicated with by runner (4), and runner (4) is provided with deep bead (7) near an end of reactor pit (5), and reactor cavity (3) top has air release hole (8).
2. the non-active heap of integral reactor according to claim 1 chamber flow passage system is characterized in that: also comprise built-in material-changing water tank (1), described built-in material-changing water tank (1) is connected with reactor cavity (3) by isolation valve (2).
3. the non-active heap of integral reactor according to claim 1 chamber flow passage system, is characterized in that: be provided with grid filter screen (6) on the path of runner (4).
4. the non-active heap of integral reactor according to claim 3 chamber flow passage system, it is characterized in that: grid filter screen (6) is steel aperture plate lattice structure.
5. the non-active heap of the described integral reactor of any one chamber flow passage system according to claim 1-4, is characterized in that: be provided with non-kinetic energy hydrogen recombiner (9) in air release hole (8) top or air release hole (8).
6. the non-active heap of the described integral reactor of any one chamber flow passage system according to claim 1-4, it is characterized in that: air release hole (8) are communicated with containment hall (10).
7. the non-active heap of the described integral reactor of any one chamber flow passage system according to claim 1-4, it is characterized in that: described runner (4) is L shaped runner.
8. the non-active heap of the described integral reactor of any one chamber flow passage system according to claim 1-4, it is characterized in that: the end that runner (4) is communicated with reactor cavity (3) is positioned at reactor cavity (3) minimum point.
9. the application process of the non-active heap of integral reactor chamber flow passage system, is characterized in that: when the image reactor loss of-coolant accident (LOCA) occurs, comprise the steps:
Step 1: start reactor high pressure and middle pressure safety injection system;
Step 2: after question response heap high pressure and middle pressure peace are annotated and completed, isolation valve (2) is opened, the water of built-in material-changing water tank (1) flows to reactor pit (5) by runner after relying on gravity piii reactor chamber (3) again, and current flood reactor pit (5), reactor cavity (3) successively;
Step 3: after built-in material-changing water tank (1) and reactor cavity (3) water level balance, built-in material-changing water tank (1) gravity water filling automatic stop;
Step 4: when carry out step 2, open non-active hydrogen recombiner (9), reactor cavity (3) internal cause loss of-coolant accident (LOCA) and cooled reactor pressure vessel and the steam that produces and hydrogen diffuse to reactor hall (10) by air release hole (8) under the air pressure self-poise drives, non-active hydrogen recombiner (9) can be released into reactor reactor cavity (3) after major accident hydrogen is diffusing to the front high efficiency composition nearby in containment hall (10).
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Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103971762A (en) * 2014-05-05 2014-08-06 中广核(北京)仿真技术有限公司 Containment vessel for nuclear power plant
CN105654996A (en) * 2014-12-01 2016-06-08 上海核工程研究设计院 Safe bunker structure of reactor
CN106869537A (en) * 2017-02-15 2017-06-20 中国科学院合肥物质科学研究院 A kind of factory building structures suitable for reactor coupled system
CN106898389A (en) * 2015-12-21 2017-06-27 中国核动力研究设计院 A kind of constrain cooling system of inherently safe containment
CN109887624A (en) * 2019-03-06 2019-06-14 中国核动力研究设计院 Analyses of LOCA Long-term cooling system when modular rickle containment isolated failure
CN111899901A (en) * 2020-08-12 2020-11-06 中国核动力研究设计院 Passive and active combined molten material in-pile retention cooling system

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5272737A (en) * 1990-09-17 1993-12-21 Hitachi, Ltd. Nuclear reactor installation
US6243432B1 (en) * 1997-06-09 2001-06-05 General Electric Company Modified passive containment cooling system for a nuclear reactor
CN2901504Y (en) * 2006-05-25 2007-05-16 中国船舶重工集团公司第七一八研究所 Hydrogen and oxygen compounding device without external power supply
CN101836262A (en) * 2007-10-22 2010-09-15 法国原子能及替代能源委员会 Nuclear reactor with improved cooling in an accident situation
CN102169733A (en) * 2011-02-14 2011-08-31 中国核电工程有限公司 Passive and active combined special safety system for nuclear power plant

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5272737A (en) * 1990-09-17 1993-12-21 Hitachi, Ltd. Nuclear reactor installation
US6243432B1 (en) * 1997-06-09 2001-06-05 General Electric Company Modified passive containment cooling system for a nuclear reactor
CN2901504Y (en) * 2006-05-25 2007-05-16 中国船舶重工集团公司第七一八研究所 Hydrogen and oxygen compounding device without external power supply
CN101836262A (en) * 2007-10-22 2010-09-15 法国原子能及替代能源委员会 Nuclear reactor with improved cooling in an accident situation
CN102169733A (en) * 2011-02-14 2011-08-31 中国核电工程有限公司 Passive and active combined special safety system for nuclear power plant

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103971762A (en) * 2014-05-05 2014-08-06 中广核(北京)仿真技术有限公司 Containment vessel for nuclear power plant
CN105654996A (en) * 2014-12-01 2016-06-08 上海核工程研究设计院 Safe bunker structure of reactor
CN106898389A (en) * 2015-12-21 2017-06-27 中国核动力研究设计院 A kind of constrain cooling system of inherently safe containment
CN106869537A (en) * 2017-02-15 2017-06-20 中国科学院合肥物质科学研究院 A kind of factory building structures suitable for reactor coupled system
CN106869537B (en) * 2017-02-15 2018-04-10 中国科学院合肥物质科学研究院 A kind of factory building structures suitable for reactor coupled system
CN109887624A (en) * 2019-03-06 2019-06-14 中国核动力研究设计院 Analyses of LOCA Long-term cooling system when modular rickle containment isolated failure
CN111899901A (en) * 2020-08-12 2020-11-06 中国核动力研究设计院 Passive and active combined molten material in-pile retention cooling system

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