JPS5491697A - Coolant loss accident prevention type atomic power plant - Google Patents

Coolant loss accident prevention type atomic power plant

Info

Publication number
JPS5491697A
JPS5491697A JP15879877A JP15879877A JPS5491697A JP S5491697 A JPS5491697 A JP S5491697A JP 15879877 A JP15879877 A JP 15879877A JP 15879877 A JP15879877 A JP 15879877A JP S5491697 A JPS5491697 A JP S5491697A
Authority
JP
Japan
Prior art keywords
piping
coolant
breaking
pipe
steam drum
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Granted
Application number
JP15879877A
Other languages
Japanese (ja)
Other versions
JPS5836760B2 (en
Inventor
Sadao Hatsutori
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Doryokuro Kakunenryo Kaihatsu Jigyodan
Power Reactor and Nuclear Fuel Development Corp
Original Assignee
Doryokuro Kakunenryo Kaihatsu Jigyodan
Power Reactor and Nuclear Fuel Development Corp
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Doryokuro Kakunenryo Kaihatsu Jigyodan, Power Reactor and Nuclear Fuel Development Corp filed Critical Doryokuro Kakunenryo Kaihatsu Jigyodan
Priority to JP52158798A priority Critical patent/JPS5836760B2/en
Priority to CA317,217A priority patent/CA1108315A/en
Publication of JPS5491697A publication Critical patent/JPS5491697A/en
Publication of JPS5836760B2 publication Critical patent/JPS5836760B2/en
Expired legal-status Critical Current

Links

Classifications

    • 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

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

PURPOSE: To provide a large diameter piping system for communication pipe to join main steam piping, water supply piping and steam drum and bottom header for pipe breaking accident prevention and reduction of coolant loss speed during accident.
CONSTITUTION: Large diameter piping system is provided for communication pipe to join main steam piping 64, water supply piping 70 and steam drum 54 and bottom header 60. While this piping system provides a clearance between piping and piping insertion hole to allow a slight movement thereof, large pipe movement can be prevented. Further, whenever an occurence of piping breaking accident caused by water level variation of steam drum 54 is detected, stop valve 90 is opened, communicating condenser pump 68 and condenser storage tank 72, supplying large amount of coolant according to location of breaking with valve control, allowing the loss of reactor coolant and the exposure phenomenon of core to prevent.
COPYRIGHT: (C)1979,JPO&Japio
JP52158798A 1977-12-28 1977-12-28 Nuclear power plant that prevents loss of coolant accidents Expired JPS5836760B2 (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
JP52158798A JPS5836760B2 (en) 1977-12-28 1977-12-28 Nuclear power plant that prevents loss of coolant accidents
CA317,217A CA1108315A (en) 1977-12-28 1978-12-01 Nuclear power plant capable of preventing coolant failure accident

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP52158798A JPS5836760B2 (en) 1977-12-28 1977-12-28 Nuclear power plant that prevents loss of coolant accidents

Publications (2)

Publication Number Publication Date
JPS5491697A true JPS5491697A (en) 1979-07-20
JPS5836760B2 JPS5836760B2 (en) 1983-08-11

Family

ID=15679572

Family Applications (1)

Application Number Title Priority Date Filing Date
JP52158798A Expired JPS5836760B2 (en) 1977-12-28 1977-12-28 Nuclear power plant that prevents loss of coolant accidents

Country Status (2)

Country Link
JP (1) JPS5836760B2 (en)
CA (1) CA1108315A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111540483A (en) * 2020-05-15 2020-08-14 中国核动力研究设计院 Method for coping with small-sized crevasse loss of coolant accident in pressurized water reactor nuclear power plant

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111540483A (en) * 2020-05-15 2020-08-14 中国核动力研究设计院 Method for coping with small-sized crevasse loss of coolant accident in pressurized water reactor nuclear power plant
CN111540483B (en) * 2020-05-15 2022-02-11 中国核动力研究设计院 Method for coping with small-sized crevasse loss of coolant accident in pressurized water reactor nuclear power plant

Also Published As

Publication number Publication date
JPS5836760B2 (en) 1983-08-11
CA1108315A (en) 1981-09-01

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