KR840000944A - Manual stop of pressurized water reactor - Google Patents

Manual stop of pressurized water reactor Download PDF

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Publication number
KR840000944A
KR840000944A KR1019820002496A KR820002496A KR840000944A KR 840000944 A KR840000944 A KR 840000944A KR 1019820002496 A KR1019820002496 A KR 1019820002496A KR 820002496 A KR820002496 A KR 820002496A KR 840000944 A KR840000944 A KR 840000944A
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South Korea
Prior art keywords
reactor
pressurizer
steam
upper region
lag
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KR1019820002496A
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Korean (ko)
Inventor
도날드 뮤직 찰스
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엘던 에이취. 루더
컴버스쳔 엔지니어링, 인코퍼레이티드
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Application filed by 엘던 에이취. 루더, 컴버스쳔 엔지니어링, 인코퍼레이티드 filed Critical 엘던 에이취. 루더
Publication of KR840000944A publication Critical patent/KR840000944A/en

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    • DTEXTILES; PAPER
    • D02YARNS; MECHANICAL FINISHING OF YARNS OR ROPES; WARPING OR BEAMING
    • D02GCRIMPING OR CURLING FIBRES, FILAMENTS, THREADS, OR YARNS; YARNS OR THREADS
    • D02G3/00Yarns or threads, e.g. fancy yarns; Processes or apparatus for the production thereof, not otherwise provided for
    • D02G3/22Yarns or threads characterised by constructional features, e.g. blending, filament/fibre
    • D02G3/26Yarns or threads characterised by constructional features, e.g. blending, filament/fibre with characteristics dependent on the amount or direction of twist
    • 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
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Engineering & Computer Science (AREA)
  • Mechanical Engineering (AREA)
  • Textile Engineering (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

내용 없음No content

Description

가압 경수로형 원자로의 수동정지Manual stop of pressurized water reactor

본 내용은 요부공개 건이므로 전문내용을 수록하지 않았음As this is a public information case, the full text was not included.

제1도는 가압경수로형 원자로의 핵 증기 공급 시스템에 대한 계통도. 제2도는 원자로 냉각제 시스템에 대한 가압기의 관계를 그린 계통도.1 is a schematic diagram of a nuclear steam supply system for a PWR reactor. 2 is a schematic diagram of the pressurizer's relationship to the reactor coolant system.

Claims (5)

원자로를 가지는 원자로 냉각시스템과, 원자로 출구를 증기 발생기에 연결하는 온 래그 배관과, 증기 발생기를 원자로 입구에 연결하는 냉 래그 배관과, 일차 냉각제를 원자로 냉각 시스템을 통해 순환시키기 위한 펌핑수단과, 상기온 래그 배관으로써 급증선을 통하여 유체가 소통되며 물이 채워진 하부영역과 접촉하여 증기가 채워진 상부영역을 가지도록 정상적으로 동작되는 가압기를 포함하는 가압경수로 형 원자로 공급시스템에 있어서.A reactor cooling system having a reactor, an on lag pipe connecting the reactor outlet to the steam generator, a cold lag pipe connecting the steam generator to the reactor inlet, pumping means for circulating the primary coolant through the reactor cooling system, and In a pressurized water reactor reactor supply system comprising a pressurizer which is normally operated to have an upper region filled with steam by contacting a lower region filled with water and communicating fluid through a sudden increase in on-lag piping. 개선된 가압기가 원자로 냉각시스템으로부터의 유동이 급증된 냉각제를 수동으로 이송하고 상기 급증된 냉각제를 가압기의 상부영역내로 방류시키기 위해 상기 상부 영역에 배치되며, 이로써 원자로 냉각제의 일부가 상기 상부영역에서 증기와 함께 혼합되는 도관 수단을 포함하는 것을 특징으로 하는 가압경수로형 원자로.An improved pressurizer is placed in the upper region for manually transferring the rapidly increasing coolant from the reactor cooling system and for discharging the increased coolant into the upper region of the pressurizer, whereby a portion of the reactor coolant is vaporized in the upper region. And a conduit means mixed with the pressurized water reactor. 제1항의 개선된 가압기에 있어서, 상기 도관수단이 액체가 채워진 하부영역에서 개방 종단을 그리고 증기가 채워진 상부영역에서 다른 개방종단을 가지며, 가압기 내에 고정되어 지지되는 수직으로 배치된 관으로 구성되는 것을 특징으로 하는 가압 경수로형원자로.The improved pressurizer of claim 1, wherein the conduit means consists of a vertically arranged tube having an open end in the lower region filled with liquid and another open end in the upper region filled with steam, and fixed and supported in the press. Pressurized water reactor reactor. 제1항의 개선된 가압기에 있어서, 상기 방류용 수단이 방류된 물을 증기가 채워진 상부영역내로 분사하기 위한 수단을 포함하는 것을 특징으로 하는 가압 경수로형 원자로.3. The pressurized water reactor of claim 1, wherein the means for discharging comprises means for injecting the discharged water into a steam filled upper region. 원자로와, 차례로 제이 냉각 루우프와 열전달 관계에 있는 증기 발생기에 원자로 출구를 연결하는 온 래그 배관과, 증기 발생기를 원자로 입구에 연결하는 냉 래그배관과, 일차 냉각제를 원자로 냉각 시스템을 통해 순환하기 위한 수단으로 구성되는 일차 냉각 시스템을 포함하며, 원자로가 전동력 정격값 위에 있는 평균 일차 냉각제의 피크값에서 원자로 동력이 본질적으로 소멸열 레벨로 강화될만한 부의 감속제 온도 반응계수를 가지며, 또한 여기서 급증선을 통하여 상기 온 래그 배관과 유체가 소통되는 가압기를 포함하는 가압경수로형 핵증기 공급시스템에 있어서, 가압기가 액체로 채워진 하부영역과 접촉하는 증기가 채워진 상부영역을 가지며, 상기 피크온도에 대응하는 일차 냉각 시스템에서의 물체적의 증가는 상기 가압기에서 증기체적을 붕괴시키지 않고 상기 가압기에 허용될 만한 규모인 것을 특징으로 하는 가압 경수로 형원자로.On lag piping connecting the reactor outlet to a steam generator in heat transfer relationship, in turn with the J cooling loop, a cold lag piping connecting the steam generator to the reactor inlet, and means for circulating primary coolant through the reactor cooling system. A primary coolant system consisting of: a reactor having a negative retarder temperature response coefficient at which the reactor power is essentially enhanced to an extinction heat level at the peak value of the average primary coolant above the power rating; A pressurized water reactor-type nuclear steam supply system including a pressurizer in fluid communication with the on-lag pipe, wherein the pressurizer has a upper region filled with steam in contact with a lower region filled with a liquid and corresponds to the peak temperature. Increasing the volume of the vapor at A pressurized light-water reactor type reactor characterized in that the scale is acceptable to the pressurizer without collapse. 제6항의 개선된 가압기에 있어서, 가압기가 증기 발생기를 통하여 2차 루우프로 전달되는 열보다더 큰 원자로에서 발생된 열의 결과로서 상기 일차 냉각제의 평균 피크온도가 발생하는 어떠한 과도기의 지속 시간을 통하여 증기 및 액체가 거기에서 포화상태로 유지될 만한 규모인 것을 특징으로 하는 가압경수로형 원자로.In the improved pressurizer of claim 6, the steam is produced through the duration of any transition period in which the average peak temperature of the primary coolant occurs as a result of heat generated in the reactor larger than the heat from which the pressurizer is transferred to the secondary loop through the steam generator. And a scale such that the liquid can remain saturated there. ※ 참고사항 : 최초출원 내용에 의하여 공개하는 것임.※ Note: The disclosure is based on the initial application.
KR1019820002496A 1981-07-07 1982-06-03 Manual stop of pressurized water reactor KR840000944A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US28113881A 1981-07-07 1981-07-07
US281138 1981-07-07

Publications (1)

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KR840000944A true KR840000944A (en) 1984-03-26

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US8681928B2 (en) * 2011-05-16 2014-03-25 Babcock & Wilcox Canada Ltd. Pressurizer baffle plate and pressurized water reactor (PWR) employing same
JP6505889B1 (en) * 2018-02-28 2019-04-24 三菱重工業株式会社 Abnormality alleviation facility for nuclear reactor and method for judging adherence of control rod
WO2024112086A1 (en) * 2022-11-22 2024-05-30 한국원자력연구원 Light water reactor for oil sand mining having mid-loop applied thereto

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