JPH0527076B2 - - Google Patents

Info

Publication number
JPH0527076B2
JPH0527076B2 JP58243769A JP24376983A JPH0527076B2 JP H0527076 B2 JPH0527076 B2 JP H0527076B2 JP 58243769 A JP58243769 A JP 58243769A JP 24376983 A JP24376983 A JP 24376983A JP H0527076 B2 JPH0527076 B2 JP H0527076B2
Authority
JP
Japan
Prior art keywords
pressure
reactor
rupture
water level
coolant
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.)
Expired - Lifetime
Application number
JP58243769A
Other languages
English (en)
Japanese (ja)
Other versions
JPS60135892A (ja
Inventor
Takashi Ikeda
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 JP58243769A priority Critical patent/JPS60135892A/ja
Publication of JPS60135892A publication Critical patent/JPS60135892A/ja
Publication of JPH0527076B2 publication Critical patent/JPH0527076B2/ja
Granted 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)
JP58243769A 1983-12-26 1983-12-26 原子炉の非常時の減圧方法およびその装置 Granted JPS60135892A (ja)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58243769A JPS60135892A (ja) 1983-12-26 1983-12-26 原子炉の非常時の減圧方法およびその装置

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58243769A JPS60135892A (ja) 1983-12-26 1983-12-26 原子炉の非常時の減圧方法およびその装置

Publications (2)

Publication Number Publication Date
JPS60135892A JPS60135892A (ja) 1985-07-19
JPH0527076B2 true JPH0527076B2 (enExample) 1993-04-20

Family

ID=17108699

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58243769A Granted JPS60135892A (ja) 1983-12-26 1983-12-26 原子炉の非常時の減圧方法およびその装置

Country Status (1)

Country Link
JP (1) JPS60135892A (enExample)

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS59200994A (ja) * 1983-04-28 1984-11-14 株式会社東芝 自動減圧系

Also Published As

Publication number Publication date
JPS60135892A (ja) 1985-07-19

Similar Documents

Publication Publication Date Title
Cao et al. Study on reduction of pressure oscillation in low-velocity steam jet condensation
US3114414A (en) Nuclear vapor generating apparatus
US11476010B2 (en) Cooling method for reactor molten core melt and cooling control system for reactor molten core
JPS62480B2 (enExample)
JPH085772A (ja) 原子炉格納容器
Kukita et al. The effects of break location on PWR small break LOCA: Experimental study at the ROSA-IV LSTF
JP2016109503A5 (enExample)
JPH0527076B2 (enExample)
Kukita et al. Summary of ROSA-IV LSTF first-phase test program—integral simulation of PWR small-break LOCAs and transients
CN103426484A (zh) 一种防止反应堆堆内熔融物熔损压力容器的方法以及用于实施这种方法的系统
Kawanishi et al. Experimental study on heat removal during cold leg small break LOCAs in PWRs
Asaka et al. Intentional depressurization of steam generator secondary side during a PWR small-break loss-of-coolant accident
Xu et al. Critical flow in convergent-divergent nozzles with cavity nucleation model
JPS6123518B2 (enExample)
JPS60151592A (ja) 非常用原子炉自動減圧方法及び装置
Shumway General features of emergency core cooling systems
CA3066230A1 (en) Cooling method for reactor molten core melt and cooling control system for reactor molten core
JPS6038692A (ja) 原子炉非常用炉心冷却系
JPH02222877A (ja) 原子炉余熱除去系ポンプウォーミング装置
Akimoto et al. Pressure drop through broken cold leg during reflood phase of loss-of-coolant accident of pressurized water reactor
JPS59126289A (ja) 原子炉の破断検知装置
JPS60151593A (ja) 沸騰水形原子炉の自動減圧装置
Zhiyun et al. Simulation Analysis on the Pressurizer Degassing Sub-System of Module Small Reactor (ACP100)
JPS60231200A (ja) 異常時原子炉出力制御装置
JPH0631810B2 (ja) 原子炉停止時運転制御方法