KR940010120A - Passive pressurized water reactor - Google Patents

Passive pressurized water reactor Download PDF

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Publication number
KR940010120A
KR940010120A KR1019920019163A KR920019163A KR940010120A KR 940010120 A KR940010120 A KR 940010120A KR 1019920019163 A KR1019920019163 A KR 1019920019163A KR 920019163 A KR920019163 A KR 920019163A KR 940010120 A KR940010120 A KR 940010120A
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KR
South Korea
Prior art keywords
reactor
passive
containment vessel
water tank
pressurized water
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Application number
KR1019920019163A
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Korean (ko)
Other versions
KR960011210B1 (en
Inventor
장순흥
노희천
백원필
이성욱
Original Assignee
천성순
한국과학기술원
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Application filed by 천성순, 한국과학기술원 filed Critical 천성순
Priority to KR1019920019163A priority Critical patent/KR960011210B1/en
Publication of KR940010120A publication Critical patent/KR940010120A/en
Application granted granted Critical
Publication of KR960011210B1 publication Critical patent/KR960011210B1/en

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • 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)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

본 발명은 기존의 원자로 냉각시스템(Reactor Coolant System)을 기본으로 여기에 피동안전시스템(Passive Safty System) 개념을 결합하여 냉각재 회로의 수가 2개이면서도 그 출력을 1000MWe 이상으로 올릴수 있는 피동형 가압경수로(Passive Pressurized Water Reaetor)에 관한 것이다.The present invention is based on the existing reactor cooling system (Reactor Coolant System) by combining the concept of passive Safty System (Passive Safty System) Passive pressure light path (Passive) that can increase the output of more than 1000MWe while having the number of coolant circuits Pressurized Water Reaetor).

본 발명에 의한 원자로의 주요계통은 원자로 냉각시스템과 피동안전시스템 (Passive Safety Syustem)으로 구성된다. 원자로냉각시스템은 핵분열을 제어가능한 상태로 일으키고 핵분열 결과 발생한 에너지를 이용하여 터빈 발전기 구동에 필요한 수증기를 생산하는 계통으로, 원자로 1기, 증기발생기 2기 가압기 1개, 원자로냉각재펌프 2대 및 관련 배관으로 구성된다.The main system of the reactor according to the present invention is composed of a reactor cooling system and a passive safety system. The reactor cooling system is a system that produces nuclear fission in a controllable state and uses the energy generated as a result of nuclear fission to produce steam for driving a turbine generator. One reactor, one steam generator, one pressurizer, two reactor coolant pumps and related piping It consists of.

Description

피동형 가압경수로Passive pressurized water reactor

본 내용은 요부공개 건이므로 전문내용을 수록하지 않았음Since this is an open matter, no full text was included.

제1도는 본 발명에 따른 피동형 가압경수로의 전체구성도,1 is an overall configuration diagram of a passive pressure light reactor according to the present invention,

제2도는 본 발명에 의한 피동형 가압경수로의 측면도.2 is a side view of a passive pressure light reactor according to the present invention.

Claims (3)

피동형 가압경수로에 있어서, 고온관(14A 및 14B)으로 원자로(1)에 각각 연결된 제1증기발생기 및 제2증기발생기(11A및 11B)와, 상기 각 증기 발생기(11A및 11B)와는 펌프흡입관(16A, l6B 및 16C, 16D)으로, 상기 원자로(1)와는 저온관(15A, 15B 및 15C, 15D)으로 연결된 4기의 원자로 냉각 펌프(12A, 12B 및 12C, 12D)와, 가압기 연결관(17)을 통하여 상기 고온관(14A)에 연결되는 가압기(13)와, 핵연료 교환용수 탱크(24)내에 설치되며, 상기 각 고온관(14A 및 14B) 및 원자로용기 직접주입관(21A 및 21B)에 연결되는 2기의 열교환기(31A 및 31B)와, 상기 각 원자로용기 직접주입관(21A 및 21B)에 순차적으로 연결되는 중간압 주입수 탱크(23A 및 23B) 및 고압 주입수탱크(22A, 24B)와, 상기 가압기(13)상부에 연결되고 또한 상기 핵연료 교환용수탱크(24) 및 각 고압주입수 탱크(22A 및 22B)와 연결된 자동감압부(26A 및 26B)를 구비하여 격납용기 내에 구성된 것을 특징으로 하는 피동형 가압경수로.In the passive pressurized water reactor, the first steam generator and the second steam generators 11A and 11B connected to the reactor 1 by hot pipes 14A and 14B, respectively, and each of the steam generators 11A and 11B and a pump suction pipe ( 16A, l6B and 16C, 16D, four reactor cooling pumps 12A, 12B and 12C, 12D connected to the reactor 1 with cold tubes 15A, 15B and 15C, 15D, and pressurizer connections ( 17 is installed in the pressurizer 13 connected to the hot tube 14A and the nuclear fuel exchange water tank 24 through the hot tube 14A, and each of the hot tube 14A and 14B and the reactor vessel direct injection tube 21A and 21B. Two heat exchangers 31A and 31B connected to each other, an intermediate pressure injection water tank 23A and 23B and a high pressure injection water tank 22A, which are sequentially connected to the respective reactor vessel direct injection pipes 21A and 21B, respectively. 24B) and an automatic pressure reduction connected to the pressurizer 13 and connected to the nuclear fuel exchange water tank 24 and each of the high pressure injection water tanks 22A and 22B. A passive pressurized water reactor comprising sections (26A and 26B) configured in a containment vessel. 제1항에 있어서, 상기 격납용기는, 금속격납용기(41) 및 그외부의 콘크리트 외벽(42)으로 구성되며, 상기 콘크리트 외벽(42)에는 각각 공기유입구(42A)와, 공기 유출구(42B)가 각각 구성되어 공기가 상기 금속격납용기(42)와 상기 콘크리트 외벽(42)간의 공간을 자연순환하도록 구성한 것을 특징으로 하는 피동형 가압경수로.2. The containment vessel of claim 1, wherein the containment vessel comprises a metal containment vessel (41) and an outer concrete outer wall (42), each of which has an air inlet (42A) and an air outlet (42B). And each of which is configured to allow air to naturally circulate the space between the metal containment vessel (42) and the concrete outer wall (42). 제2항에 있어서, 상기 콘크리트 외벽(42)은 그 상단에 격납용기 냉각수 탱크(43)를 설치한 것을 특징으로 하는 피동형 가압경수로.3. The passive pressurized water path as claimed in claim 2, wherein the concrete outer wall (42) is provided with a containment vessel cooling water tank (43) at an upper end thereof. ※ 참고사항 : 최초출원 내용에 의하여 공개하는 것임.※ Note: The disclosure is based on the initial application.
KR1019920019163A 1992-10-19 1992-10-19 A pressurized water reactor of a passive type KR960011210B1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
KR1019920019163A KR960011210B1 (en) 1992-10-19 1992-10-19 A pressurized water reactor of a passive type

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
KR1019920019163A KR960011210B1 (en) 1992-10-19 1992-10-19 A pressurized water reactor of a passive type

Publications (2)

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KR940010120A true KR940010120A (en) 1994-05-24
KR960011210B1 KR960011210B1 (en) 1996-08-21

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR100563254B1 (en) * 2000-12-01 2006-03-27 한국과학기술원 A Pressurized Water Reactor Using Cooling Devices

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR101029444B1 (en) * 2010-06-30 2011-04-14 한국수력원자력 주식회사 External reactor vessel cooling system using a dedicated water storage tank and a seal plate

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR100563254B1 (en) * 2000-12-01 2006-03-27 한국과학기술원 A Pressurized Water Reactor Using Cooling Devices

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