JPS60135892A - 原子炉の非常時の減圧方法およびその装置 - Google Patents
原子炉の非常時の減圧方法およびその装置Info
- Publication number
- JPS60135892A JPS60135892A JP58243769A JP24376983A JPS60135892A JP S60135892 A JPS60135892 A JP S60135892A JP 58243769 A JP58243769 A JP 58243769A JP 24376983 A JP24376983 A JP 24376983A JP S60135892 A JPS60135892 A JP S60135892A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- pressure
- rupture
- emergency
- water level
- 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
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)
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 true JPS60135892A (ja) | 1985-07-19 |
| JPH0527076B2 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) |
Citations (1)
| 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 |
-
1983
- 1983-12-26 JP JP58243769A patent/JPS60135892A/ja active Granted
Patent Citations (1)
| 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 |
|---|---|
| JPH0527076B2 (enExample) | 1993-04-20 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US3114414A (en) | Nuclear vapor generating apparatus | |
| Min et al. | Experimental verification on the integrity and performance of the passive residual heat removal system for a SMART design with VISTA-ITL | |
| Jiang et al. | Simulation analysis of an open natural circulation for the passive residual heat removal in IPWR | |
| Sui et al. | Investigation on response of hpr1000 under different mitigation strategies after sgtr accident | |
| Kukita et al. | The effects of break location on PWR small break LOCA: Experimental study at the ROSA-IV LSTF | |
| JPS60135892A (ja) | 原子炉の非常時の減圧方法およびその装置 | |
| 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 | |
| CN103426485B (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 | |
| Shang et al. | Research on operating characteristics of AP1000 automatic depressurization system under typical accident condition | |
| Xing et al. | Depressurization strategy of China's advanced pressurized water reactor under typical accidents | |
| Shumway | General features of emergency core cooling systems | |
| Park et al. | Safety verification for the ECCS driven by the electrically 4 trains during LBLOCA reflood phase using ATLAS | |
| JPS60151592A (ja) | 非常用原子炉自動減圧方法及び装置 | |
| JPS6038692A (ja) | 原子炉非常用炉心冷却系 | |
| JPS60213887A (ja) | 原子炉の配管破断検出方法及び装置 | |
| Zhiyun et al. | Simulation Analysis on the Pressurizer Degassing Sub-System of Module Small Reactor (ACP100) | |
| Zhai et al. | Development and application of an external cooling model for pressure vessels based on the ISAA program | |
| Polkinghorne et al. | Analysis of an advanced test reactor small-break loss-of-coolant accident with an engineered safety feature to automatically trip the primary coolant pumps | |
| Kim et al. | Study on the steam line break accident for Kori unit-1 | |
| Wang et al. | Using the RELAP5/MOD2 code under low-pressure/low-temperature loss-of-coolant-accident conditions | |
| Linebarger et al. | LOFT isothermal and nuclear experiment results | |
| Schaefer et al. | Post-test analysis of two accident management experiments performed at the BETHSY test facility using the code ATHLET | |
| Park et al. | Experimental Study on the Intermediate Break Loss of Coolant Accident (IBLOCA) with Total failure of Safety Injection Pumps | |
| Lee et al. | Assessment of SPACE code for multiple failure accident: 1% Cold Leg Break LOCA with HPSI failure at ATLAS Test Facility | |
| Parka et al. | The Effect of External Vessel Cooling for a 2 inch LOCA Severe Accident Scenario at SMART with MIDAS/SMR |