JPS6222095A - 沸騰水型原子力発電所の定期検査時の制御棒駆動機構の交換作業方法およびこれに用いる制御棒駆動機構 - Google Patents
沸騰水型原子力発電所の定期検査時の制御棒駆動機構の交換作業方法およびこれに用いる制御棒駆動機構Info
- Publication number
- JPS6222095A JPS6222095A JP60161669A JP16166985A JPS6222095A JP S6222095 A JPS6222095 A JP S6222095A JP 60161669 A JP60161669 A JP 60161669A JP 16166985 A JP16166985 A JP 16166985A JP S6222095 A JPS6222095 A JP S6222095A
- Authority
- JP
- Japan
- Prior art keywords
- full
- control
- drive motor
- detector
- detection
- 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60161669A JPS6222095A (ja) | 1985-07-22 | 1985-07-22 | 沸騰水型原子力発電所の定期検査時の制御棒駆動機構の交換作業方法およびこれに用いる制御棒駆動機構 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60161669A JPS6222095A (ja) | 1985-07-22 | 1985-07-22 | 沸騰水型原子力発電所の定期検査時の制御棒駆動機構の交換作業方法およびこれに用いる制御棒駆動機構 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6222095A true JPS6222095A (ja) | 1987-01-30 |
| JPH0448197B2 JPH0448197B2 (enExample) | 1992-08-06 |
Family
ID=15739586
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60161669A Granted JPS6222095A (ja) | 1985-07-22 | 1985-07-22 | 沸騰水型原子力発電所の定期検査時の制御棒駆動機構の交換作業方法およびこれに用いる制御棒駆動機構 |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6222095A (enExample) |
-
1985
- 1985-07-22 JP JP60161669A patent/JPS6222095A/ja active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0448197B2 (enExample) | 1992-08-06 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US11842819B2 (en) | Method for replacing a cesium trap and cesium trap assembly thereof | |
| EP0538407A1 (en) | Nuclear reactor with bi-level core | |
| CN103163397A (zh) | 核电站通用模拟量板件检测系统和方法 | |
| US5204053A (en) | Bi-level fuel management method for boiling-water nuclear reactor | |
| US6650722B1 (en) | Hydraulic control unit transponder card | |
| JPS6222095A (ja) | 沸騰水型原子力発電所の定期検査時の制御棒駆動機構の交換作業方法およびこれに用いる制御棒駆動機構 | |
| Hurt III et al. | Oak Ridge research reactor quarterly report: April, May, and June of 1973 | |
| Fryer et al. | Identification of failed fuel element | |
| JPH04168398A (ja) | 原子炉監視装置 | |
| Lewis et al. | Canadian operating experience with heavy water power reactors | |
| Abul-Faraj | Evaluation of human error in high temperature gas cooled reactor | |
| JPS6262286A (ja) | 沸騰水型原子炉炉心 | |
| Kapoor et al. | Unusual occurrences in fast breeder test reactor | |
| JPS59136688A (ja) | 原子炉用中性子検出装置 | |
| JPS61202191A (ja) | 核燃料貯蔵庫及び装荷方法 | |
| JPH10239476A (ja) | 制御棒駆動機構用位置指示装置 | |
| Tabor et al. | OAK RIDGE RESEARCH REACTOR QUARTERLY REPORT, OCTOBER, NOVEMBER, AND DECEMBER OF 1969. | |
| JPS60165592A (ja) | 制御棒駆動機構監視装置 | |
| Hurt III et al. | Oak Ridge research reactor quarterly report, October--December 1970 | |
| VASUDEVAN et al. | UNUSUAL OCCURENCES IN FAST BREEDER TEST REACTOR RP KAPOOR, G. SRINIVASAN, TR ELLAPPAN, PV RAMALINGAM | |
| JPH01116497A (ja) | 沸騰水型原子炉 | |
| Bickel | Impact of support system failure limitations on probabilistic safety assessment and in regulatory decision making | |
| Preda et al. | Nuclear safety enhancement of the Instrumentation and Control System at TRIGA SSR 14 MW-Romania | |
| Eggleston | PIQUA NUCLEAR POWER FACILITY SURVEILLANCE AND RECOVERY PROGRAM. Final Report. | |
| Bailey et al. | Integrity of neutron-absorbing components of LWR fuel systems |