GB2520455A - Secondary-side passive residual heat discharge system for nuclear power plant steam generator - Google Patents

Secondary-side passive residual heat discharge system for nuclear power plant steam generator Download PDF

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Publication number
GB2520455A
GB2520455A GB1504121.3A GB201504121A GB2520455A GB 2520455 A GB2520455 A GB 2520455A GB 201504121 A GB201504121 A GB 201504121A GB 2520455 A GB2520455 A GB 2520455A
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GB
United Kingdom
Prior art keywords
residual heat
pipeline
heat discharge
steam generator
water
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Application number
GB1504121.3A
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GB201504121D0 (en
GB2520455B (en
Inventor
Wei Huang
Yun Ren
Jianyong Lai
Yulong Zhang
Haiming Sui
Chang Zeng
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Nuclear Power Institute of China
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Nuclear Power Institute of China
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Publication of GB2520455A publication Critical patent/GB2520455A/en
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Publication of GB2520455B publication Critical patent/GB2520455B/en
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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/002—Component parts or details of steam boilers specially adapted for nuclear steam generators, e.g. maintenance, repairing or inspecting equipment not otherwise provided for
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • G21D3/06—Safety arrangements responsive to faults within the plant
    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

A secondary-side passive residual heat discharge system for a nuclear power plant steam generator, comprising a cooling water tank (3) filled with water and disposed on the periphery of a reactor containment casing (11), a heat exchanger (2) immersed at the bottom of the cooling water tank, a first residual heat discharge pipeline (12) having one end extend out through the containment casing and connect to the inlet of the heat exchanger, a steam pipeline isolation valve (5) disposed on the first residual heat discharge pipeline, a second residual heat discharge pipeline (13) having one end extend out through the containment casing and connect to the outlet of the heat exchanger, and a first set of isolation valves (7) disposed on the second residual heat discharge pipeline; the other end of the first residual heat discharge pipeline is connected to a steam pipeline (9) at the upper end of the steam generator (1); the other end of the second residual heat discharge pipeline is connected to the water supply pipeline (10) of the steam generator. When the whole plant has a power outage and the power plant loses the ability to discharge the residual heat of the whole active reactor core, the system can utilize the density difference between the steam and water as a driving force to operate "passively" to discharge the reactor core residual heat for an extended length of time, thus keeping the reactor in a safe state.

Description

Specification
A Secornlary-4de Passive RSdwal Heat Thscliaie Stem for A Nuclear Power Plant Steam Generator
l'eehnical Field of the Invention
The utility model discloses a residual heat discharge system in the nuclear power plant, particularly, a secondary-side passive residual heat discharge system for a nuclear power plant steam generator.
Background of the Invention
In case of power cutoff accident in the nuclear power plant (station), the main pump is 1 5 shut down, reactor coolant flow is reduced sharply and water supply at secondary side of steam generator is lost so that heat transmission capacity of steam generator is dampened.
heat of reactor core is accumulated in the reactor coolant system and system temperature is increased, in the power cutoff accident, effective discharge of residual heat relates to the safety of nuclear powcr plant (station).
in the past. we ca.n only provide water for the secondary side of steam generator through steam driven pump of auxiliary water supply system under the power cutoff accident; however, dependence on active equipment may suffer from failure in the complex accident environment. If the water supply series of steam driven pump of auxiliary water suppy system fails, the unit will lose the ability to discharge residual heat of reactor core and cannot assure the safety of nuclear power plant (station). In the desi of nuclear power pant (station), the passive technology is widely recognized and applied as a mature, reliable and advanced technology. Thereibre, it is urgent to adopt the passive residu& heat discharge system (wid.e application) at secoc.tdary side of steam generator under the power cutoff accident of nuclear power plant.
DeSled DeedpUon of the Invention The utility model aims to settle the following technical problem: In case of power cutoff accident in the nuclear power plant and missing of active residual heat discharge capacity in the reactor core, adopt steam/water density gap (gravity gap) as the driving force, operate in the "passive" model, lead. out the residual heat of reactor core for a long time and maintain the passive residual heat discharge system at secondary side of steam generator under safe status of reactor.
In order to settle the said technical problem, the technical plan of utility model is as thflows: The utility mode! discloses A secondary-side passive residual heat discharge system for a nuclear power plant steam generator and consists of the cooling water tank outside the safety casing of' reactor, heat. exchanger at the bottom of cooling water tank. No. I residual heat discharge pipeline whose end penetrates the safety casing and connected with inlet of heat exchanger, steam pipeline isolating valve in No, I residual heat discharge pipe, No. 2 residual heat discharge pipeline whose end penetrates the safety casing and connected with outlet of heat exchanger and No. I isolating valve in No. 2 residual heat discharge pipeline.
The other end of said No. I residual heat discharge pipeline is connected with the steam.
pipeline at the upper end of steam generator; the other end of No. 2 residual heat discharge pipeline is connected with the water supply pipeline of steam generator.
it also consists of the check valve in No, 2 residual heat discharge pipeline. The said check valve is coilocated between "No. 2 residual heat discharge pipeline-water supply pipe" contact and No. I isolating valve.
It also consists of the water injection pipeline. The water make-up tank and No. 2 isolating va've are coilocated in the said water injection pipeline; one end of the said water injection pipeline near water make-up tauilc is connected with No, I residuaJ heat water discharge pipeline between steam pipeline isolating valve and heat exchanger; one end of the said water injection pipeline near No. 2 isolating valve is connected with No. 2 residual heat discharge pipeline between check valve and No, I isolating valve.
The cooling water tank is in the ring structure and collocated at the outer side of safety casing. Both No. I isolating valve and No, 2 isolating valve consist of several paraHel iso] ath g valves.
The water make-up tank consists of at least one water make-up tank.
The water make-up tank consists of several parallel water make-up tanks.
The water make-up tank, No. I isolating valve and No. 2 isolating valve are collocated in the safety easing.
The water make-op tank, No. I isolating valve and No. 2 isolating valve are collocated in the safety casing.
The bottom of cooling water tank is higher than the highest point of steam generator; the bottom of water make-up tank is higher than the water supply pipeline of steam generator.
The beneficial effect of ftis utility model is as follows: In ease of power cutoff accident in the nuclear power plant and missing of active residual heat discharge capacity in the reactor core, adopt steam/water density gap (çavity gap) as the driving force, operate in the "passive" model, lead out the residual heat of reactor core for a long time and maintain the safe status of reactor.
ldption ofDnwb Fig. I refers to the schematic diagram of a secondary*side passive residual heal discharge system for a nuclear power plant slearn generator (The water make-up tank, No. I isolating valve and No. 2 isolating valve are coilocated in the safety casing).
Fig2 refers to the schematic diagram inside safety casing of the A secondary-side passive residual heal discharge system for a nuclear power plant steam generator (The water make-up tank, No. 1 isolating valve and No. 2 isolating valve are collocated outside the safety casing).
FigS refers to the schematic diagram outside safety casing of the A secondary-side passive residual heat discharge system fbr a nuclear power plant steam generator (The waler make-up tank, No. I isolating valve and No, 2 isolating valve are coliocated outside the safety casing).
in the figures: 1-Steam generator; 2-Heat exchanger; i Cooling water tank; Water make-up tank; 5 Isolating valve of steam pipeline; 6-No. 2 isolating valve; 7-No.
1 isolating valve; 8-Check valve; 9-Steam pipeline; 10 Water supply pipeline; 11-Safety casing 12-No. 1 residual heat discharge pipeline; 13-No. 2 residual heat discharge pipeline; 14-Water injection pipeline; 15 Concrete equipment compariment.
We would like to further describe the utility model according In Fig, I, Fig. 2. Fig. 3 and the embodiment, Embodiment I: As shown in Pig. 1, the utility model discloses a secondary-side passive residual heat discharge system for a nuclear power plant steam generator and consists of th.e cooling water tank $ filled with water and oulside the safety casing Ii of reactor. The said safety casing II.
of reactor is collocated with a cylindrical shell; the said cooling water tank 3 is in the ring structure and collocated at a rather high position outside the safety casing 11; the civil structure is compatible with the safety casing. The water make-up structure and water discharge structure are eollocated in the cooling water tank 3 in order to make up water to cooling water tank 3 before start and discharge water itt the maintenance.
The heat exchanger 2 is immersed at the bottom of said cooling water tank 3; the water inlet and water outlet are collocated in the upper head and lower head.
One end of No. 1 residual heat discharge pipeline 12 penetrates the safety casing 11 and connects with the said heat exchanger 2; the other end is connected with the steam pipeline 9 of steam generator 1; the isolating valve 5 of steam pipeline is collocated in the safety casing 11 and said No. I residual heat discharge pipeline 12..
One end of No. 2 residual heat discharge pipeline 13 penetrates the safety casing 11 and connects with the outlet of said heat exchanger 2; the other end is connected with the water supply pipeline 10 of steam generator 1: No. 1 isolating valve 7 of two parallel isolating valves is collocated in No. 2 residual heat discharge pipeline 13.
The check vave 8 is coflocated in No-2 residual heat discharge pipeline 13 and between "No. 2 residual heat discharge pipeline 13-water supply pipeline 10" contact and No. I isolating valve 7.
The water make-up tank 4 and No. 2 isolating valve 6 (composed of two parallel isolating valves) are coilocated in the water injection pipeline 14; one end of the said water injection pipeline 14 near water make-up tank 4 is connected with. No. 1 residual heal water discharge pipeline 12 between isolating valve 5 of steam pipeline and in'et of heat exchanger 2; one end of the said water injection pipeline 14 near No. 2 isolating valve 6 is connected with No. 2 residual heat water discharge pipeline 13 between check valve 8 and No. I isolating valve 7. The water make-up tank 4 refers to a cylinder vessel with elliptical head; it is able to coliocate several water make-up tanks 4 in the water injection pipeline 14 in a parallel manner. The designed scope of total capacity of parallel water make-up tanks 4 is between iOinL7Onu3, The said No. 1 isolating valve 6. No. 2 isolating valve 7 and water make-up tank 4 are collocated in the safety easing.
Embodiment Ii: As shown in Fig. 2 and Fig. 3, the difference from Embodiment I lies in that said No. I isolating valve 6, No. 2 isolating valve 7 and water make-up tank 4 are coliocated in the concrete equipment compartment iS outside the safety easing.
Embodiment The difference from Embodiment i lies in that said No. I isolatmg valve 6 and No. 2 isolating valve 7 are collocated in the safety casing while water makeu.p tank 4 is coilocated in the concrete equipment compartment 15 outside the safety easing.
Embodiment IV: 1 0 The difference from Embodiment I lies in that said No. 1 isolating valve 6 and No. 2 i.solalln.g valve 7 are coliocated in the concrete equipment compartment 5 outside the safety casing while water makeup tank 4 is collocated in the safety casing.
Given diii: rent standard inside and outside the safety casing, the inside and outside collocation of equipment will bring about different results, For instance, different irradiation doses in the equipment structure will lead to different safety standard.
in ease of any accident, four embodiments are able to operate. The operator opens No. I isolating valve 7 of No. 2 residual heat discharge pipeline 13 and operates the system; fills condensate at secondary side of cooler 2 into the water supply pipeline 10 of steam generator I (flows into the secondary side of steam generator U; heats up condensate at secondary side by reactor coolant at primary side of steam generator I and changes into steam; flows into the inlet of cooler 2 through No. I residual heat discharge pipeline 12, transmits heat to the water of cooling water tank 3 and re-condensates into water; returns to the secondary side of steam generator I and thrms a natural circulation. The system transmits heat of reactor coolant into the cooler 2 through steam generator 1, then transmits to the water of cooling water tank 3, ultimately brings heat away through water evaporation in the cooling water tank 3 and thus assures the safety of reactor.
If the water level at secondary side of steam generator is reduced to a certain level upon normal operation of the system, the operator opens No. 2 isolating valve 4 in the water injection pipeline 14 and fills water of water makeup tank 4 into the secondary side of steam generator; in the normal operation of make-up system, the water level at secondary side of steam generator 1 is reduced-Upon termination of water filling, the operator manually closes the isolating valve in the water injection pipeitne 14.
The utility model discloses a secondary-side passive residual heat discharge syswrn for a nuclear power plant steam generator which is abbe to coilocate numerous separate series according to the ring route quantity of PWR nuclear power plant and connect with the secondary side of each steam generator. The said embodiments refer to one series, Claim

Claims (8)

1. The utility model discloses a second ary-side passive residual heat discharge system for a nuclear power plant steam generator, which is characterized that it consists of the cooling water tank outside the sa&ty casing of reactor, heat exchanger at the bottom of cooling water tank, No. I residual heat discharge pipeline whose end penetrates the safety casing and connected with inlet of heat exchanger, steam pipeline isolating valve in No. 1 residual heat discharge pipe, No. 2 residual heat discharge pipeline whose end penetrates the safety casing and connected with outlet of heat exchanger and No. 1 isolating valve in No. 2 residual heat discharge pipeline. The other end of said No. 1 residual heat discharge pipeline is connected with the steam pipeline at the upper end of steam generator; the other end of No. 2 residual heat discharge pipeline is connected with the water supply pipeline of steam generator.
2. The A secondary-side passive residual heat discharge system for a nuclear power plant steam generator is coltocated according to claim I, it is characterized that it also consists of the check valve in No. 2 residual heat discharge pipeline. The said check valve is coltocated between "No. 2 residual heat discbarge pipeline-water supply pipe" contact and No. 1 isolating valve.
3. The A secondary-side passive residual heat discharge system for a nuclear power plant steam generator is collocated according to claim 1, it is characterized that it also consists of the water injection pipeline. The water make-up tank and No. 2 isolating valve are collocated in the said water injection pipeline; one end of the said water injection pipeline near water make-up tank is connected with No. 1 residual heat water discharge pipeline between steam pipeline isolating valve and heat exchanger; one end of the said water injection pipeline near No. 2 isolating valve is connected with No, 2 residual heat discharge pipeline between check valve and No. I isolating valve.
4. The A secondary-side passive residual heat discharge system for a nuclear power plant steam generator is collocated according to claim 1, it is characterized that the cooling water tank is in the ring structure and collocated at the outer side of safety casing.
5. The A secondary-side passive residual heat discharge system for a nuclear power plant steam generator is collocated according to claim 3, it is characterized that both No. 1 isolating valve and No.2 isolating valve consist of several parallel isolating valves.
6. The A secondary-side passive residual heat discharge system for a nuclear power plant steam generator is coHocated according to claim 3, it is characterized that the water makeup tank consists of at least one water make-up tank,
7. The A secondary-side passive residual heat discharge system for a nuclear power pant steam generator is collocated according to claim 3. It is characterized that the water make--up tank consists of several parallel water make-up tanks.
8. The A secondary-side passive residual heat discharge system for a nuclear power plant steam generator is coiloca.ted according to claim 3, it is characterized that the water make-up tank, No. I isolating valve and No, 2 isolating valve are coilocatcd in the safety casing.9. i'he A secondary-side passive resi.dua heat discharge system for a nuclear power plant steam generator is collocated according to claim 3, it is characterized that the water make-up tank, No. 1 isolating valve and No, 2 isolating valve are collocated outside the safety casing.10. The A secondary-side residua heat discharge system for a nuclear power plant steam generator is collocated according to claim 3, it is characterized that the bottom of cooling water tank is higher than the highest point of steam generator; the bottom of water make-up tank is higher than the water supply pipeline of steam generator.
GB1504121.3A 2012-08-20 2013-08-19 A secondary-side passive residual heat discharge system for a nuclear power plant steam generator Active GB2520455B (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
CN201210295360.XA CN103632737A (en) 2012-08-20 2012-08-20 Passive waste heat discharge system of nuclear power station steam generator secondary side
PCT/CN2013/081733 WO2014029306A1 (en) 2012-08-20 2013-08-19 Secondary-side passive residual heat discharge system for nuclear power plant steam generator

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GB201504121D0 GB201504121D0 (en) 2015-04-22
GB2520455A true GB2520455A (en) 2015-05-20
GB2520455B GB2520455B (en) 2018-01-10

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GB (1) GB2520455B (en)
WO (1) WO2014029306A1 (en)

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CN106653109A (en) * 2016-12-30 2017-05-10 福建福清核电有限公司 Experimental research device for secondary side passive residual heat removal system (PRS)

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CN104733060A (en) * 2015-03-25 2015-06-24 东南大学 Passive residual heat removal system of marine nuclear power device
CN105070329A (en) * 2015-08-31 2015-11-18 上海核工程研究设计院 Nuclear power station secondary side passive residual heat removal system
CN105070327A (en) * 2015-08-31 2015-11-18 上海核工程研究设计院 Nuclear power station secondary side long-term waste heat removal system
CN105608979B (en) * 2016-02-23 2019-11-15 中广核研究院有限公司 The experimental rig and method of model steam generator secondary side residual heat removal system
CN105957567B (en) * 2016-05-06 2018-03-06 中国核动力研究设计院 A kind of steam generator secondary side Heat Discharging System of Chinese
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CN110164569A (en) * 2019-05-14 2019-08-23 中国舰船研究设计中心 A kind of long timeliness secondary circuit passive residual heat removal system of water surface atomic-powered ship
CN111128414B (en) * 2019-12-31 2022-07-26 中国核动力研究设计院 Active and passive combined safety system and method for nuclear power plant
CN111312055A (en) * 2020-03-17 2020-06-19 华北电力大学 Entity + virtual pressurized water reactor full-working-condition simulation platform
CN112530611A (en) * 2020-12-24 2021-03-19 上海核工程研究设计院有限公司 Advanced and simplified small-pile passive special safety system
CN112951457A (en) * 2021-03-05 2021-06-11 哈尔滨工程大学 PCS long-term heat exchange water tank with parallel channels

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Publication number Priority date Publication date Assignee Title
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GB201504121D0 (en) 2015-04-22
CN103632737A (en) 2014-03-12
WO2014029306A1 (en) 2014-02-27
GB2520455B (en) 2018-01-10

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