JPS5467883A - Reactor - Google Patents

Reactor

Info

Publication number
JPS5467883A
JPS5467883A JP13462677A JP13462677A JPS5467883A JP S5467883 A JPS5467883 A JP S5467883A JP 13462677 A JP13462677 A JP 13462677A JP 13462677 A JP13462677 A JP 13462677A JP S5467883 A JPS5467883 A JP S5467883A
Authority
JP
Japan
Prior art keywords
coolant
flowed out
vent tubes
drywell
atm
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
JP13462677A
Other languages
Japanese (ja)
Other versions
JPS5646118B2 (en
Inventor
Masanori Naito
Shinichi Kashiwai
Hisamichi Inoue
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.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP13462677A priority Critical patent/JPS5467883A/en
Publication of JPS5467883A publication Critical patent/JPS5467883A/en
Publication of JPS5646118B2 publication Critical patent/JPS5646118B2/ja
Granted legal-status Critical Current

Links

Classifications

    • 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

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

PURPOSE: To reduce the mean density of coolant passing through vent tubes at an accidental time of piping failure, by means of separating the gas and the liquid of the two phases flowed out from a breaking part of the piping, and of reducing the liquid quantity entered into the prenum chamber via vent tubes.
CONSTITUTION: When an accumulated water 71 is present, a height Lc from the floor plate of upper opening ports 61 of vent tubes 8 is made high sufficient to hold the total water flowed out within the drywell on the floor plate in a case when whole of the first coolant which is holded in the reactor vessel, is discharged. In a standard reactor of the thermal output of 3300 MW grade, the quantity of the first coolant is at 350 t, and the area of the floor is 500m2 and when the first coolant is flowed out from 70 atm. into a drywell of one atm., the flowed out water quantity becomes to 350 (1-0.37) = 220.5 t, thereby Lc= 230/500= 0.46, Lc may be specified as 50cm by means of estimating the margin. Accordingly, the materials passing through the vet tube is only steam.
COPYRIGHT: (C)1979,JPO&Japio
JP13462677A 1977-11-11 1977-11-11 Reactor Granted JPS5467883A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP13462677A JPS5467883A (en) 1977-11-11 1977-11-11 Reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP13462677A JPS5467883A (en) 1977-11-11 1977-11-11 Reactor

Publications (2)

Publication Number Publication Date
JPS5467883A true JPS5467883A (en) 1979-05-31
JPS5646118B2 JPS5646118B2 (en) 1981-10-30

Family

ID=15132763

Family Applications (1)

Application Number Title Priority Date Filing Date
JP13462677A Granted JPS5467883A (en) 1977-11-11 1977-11-11 Reactor

Country Status (1)

Country Link
JP (1) JPS5467883A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2010134280A1 (en) * 2009-05-20 2010-11-25 三菱重工業株式会社 Nuclear reactor containment structure

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2010134280A1 (en) * 2009-05-20 2010-11-25 三菱重工業株式会社 Nuclear reactor containment structure

Also Published As

Publication number Publication date
JPS5646118B2 (en) 1981-10-30

Similar Documents

Publication Publication Date Title
CH613297A5 (en) Nuclear reactor cooled by a liquid metal
US3223589A (en) Regulating method and apparatus for nuclear reactors
ES8301380A1 (en) Nuclear steam generator.
GB1078318A (en) Improvements in or relating to nuclear reactor systems
GB1102606A (en) Improvements in and relating to nuclear reactors
US4246069A (en) Heat-generating nuclear reactor
JPS5467883A (en) Reactor
US3144393A (en) Subcooled liquiod inlet fog cooled nuclear reactors
US3994777A (en) Nuclear reactor overflow line
GB795406A (en) Improvements in or relating to nuclear reactors
KR840000944A (en) Manual stop of pressurized water reactor
US3130129A (en) Nuclear reactors
US3166480A (en) Homogeneous boiling reactor
GB1205849A (en) Liquid-safety rod system for a nuclear reactor
JPS5589443A (en) Liquid metal purifier
JPS56141407A (en) High-temperature liquid pipe
JPS57105693A (en) Leakage detecting method for heat transferring tube of heat exchanger
FR2350130A1 (en) Water-steam separator esp. for (boiling water) nuclear reactor - is designed for ease of monitoring, decontamination and dismantling
JPH041517Y2 (en)
GB1059246A (en) Improvements in and relating to nuclear reactors
JPS5524621A (en) Liquid level detector of saturated liquid
JPS56107973A (en) Head power-generation device by circulating liquid
JPS52102988A (en) Pressure suppression device for reactor container
MOORE et al. Analysis of GE BWR blowdown heat transfer program, test 4906(AEC standard problem four)[Final Report]
JPS5442592A (en) Reactor fuel element