JPS60169793A - 沸騰水型原子炉 - Google Patents
沸騰水型原子炉Info
- Publication number
- JPS60169793A JPS60169793A JP59024720A JP2472084A JPS60169793A JP S60169793 A JPS60169793 A JP S60169793A JP 59024720 A JP59024720 A JP 59024720A JP 2472084 A JP2472084 A JP 2472084A JP S60169793 A JPS60169793 A JP S60169793A
- Authority
- JP
- Japan
- Prior art keywords
- heat exchanger
- pressure vessel
- liquid level
- nuclear reactor
- cooling water
- 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Production Of Liquid Hydrocarbon Mixture For Refining Petroleum (AREA)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59024720A JPS60169793A (ja) | 1984-02-13 | 1984-02-13 | 沸騰水型原子炉 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59024720A JPS60169793A (ja) | 1984-02-13 | 1984-02-13 | 沸騰水型原子炉 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS60169793A true JPS60169793A (ja) | 1985-09-03 |
| JPH0361920B2 JPH0361920B2 (Direct) | 1991-09-24 |
Family
ID=12145991
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59024720A Granted JPS60169793A (ja) | 1984-02-13 | 1984-02-13 | 沸騰水型原子炉 |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60169793A (Direct) |
-
1984
- 1984-02-13 JP JP59024720A patent/JPS60169793A/ja active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0361920B2 (Direct) | 1991-09-24 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| EP0071326B1 (en) | Nuclear power plant | |
| Ishiwatari et al. | Safety of super LWR,(I) safety system design | |
| JPS60169793A (ja) | 沸騰水型原子炉 | |
| Iwamura et al. | A concept and safety characteristics of JAERI passive safety reactor (JPSR) | |
| JPS62182697A (ja) | 原子炉冷却系 | |
| EP0170033B1 (en) | Fluid moderator control system -d2o/h2o | |
| JPS6375691A (ja) | 自然循環型原子炉 | |
| Hannerz et al. | The PIUS pressurized water reactor: aspects of plant operation and availability | |
| Amm et al. | ATWS Parameter Studies for a Tight-Lattice PWR | |
| Weisshaupl et al. | PKL small break tests and energy transport mechanisms | |
| Alekseev et al. | RBEC lead-bismuth cooled fast reactor: Review of conceptual decisions | |
| JP2718855B2 (ja) | 核燃料チャンネルおよびこれを利用した固有安全水冷却チューブ原子炉 | |
| Radkowsky et al. | Optimization of once-through uranium cycle for pressurized light water reactors | |
| Murao et al. | A Concept of Passive Safety, Pressurized Water Reactor System with Inherent Matching Nature of Core Heat Generation and Heat Removal | |
| Oka et al. | Reactor design and safety | |
| Forsberg | Passive emergency cooling systems for boiling water reactors (PECOS-BWR) | |
| JPS63195592A (ja) | 自然循環炉の出力制御装置 | |
| Naruko et al. | Retran safety analyses of the nuclear-powered ship Mutsu | |
| Fuji-IE | Control systems and transient analysis | |
| JPS63208794A (ja) | 沸騰水型原子炉 | |
| Yadigaroglu | Nuclear reactors: Physics and materials | |
| Rohatgi et al. | Steam line break and station blackout transients for proliferation-resistant hexagonal tight lattice boiling water reactor | |
| JPS6333677B2 (Direct) | ||
| Papez et al. | LOFTRAN/RETRAN Comparison Calculations for a Postulated Loss-of-Feedwater ATWS in the Sizewell ‘B’PWR | |
| Gransell et al. | Core design and dynamics of the secure district heating reactor |