KS C IEC 61250-2006 Nuclear reactors-Instrumentation and control systems important for safety-Detection of leakage in coolant systems《核反应堆 安全重要仪表和控制系统 冷却剂系统的泄漏检测》.pdf
《KS C IEC 61250-2006 Nuclear reactors-Instrumentation and control systems important for safety-Detection of leakage in coolant systems《核反应堆 安全重要仪表和控制系统 冷却剂系统的泄漏检测》.pdf》由会员分享,可在线阅读,更多相关《KS C IEC 61250-2006 Nuclear reactors-Instrumentation and control systems important for safety-Detection of leakage in coolant systems《核反应堆 安全重要仪表和控制系统 冷却剂系统的泄漏检测》.pdf(14页珍藏版)》请在麦多课文档分享上搜索。
1、KSKSKSKS SKSKSKS KSKSKS SKSKS KSKS SKS KS 2006 9 30 http:/www.kats.go.krKS C IEC 61250 KS C IEC 61250: 2006 (2011 )C IEC 61250: 2006 : ( ) ( ) ( ) : (http:/www.standard.go.kr) : : 2006 9 30 : 2011 12 28 2011-0637 : : ( 02-509-72703) (http:/www.kats.go.kr). 10 5 , . ICS 27.120.20 KS C IEC 61250: 2006
2、(2011 ) Nuclear reactors Instrumentation and control systems important for safety Detection of leakage in coolant systems 1994 1 IEC 61250 Nuclear reactors Instrumentation and control systems important for safety Detection of leakage in coolant systems , . 1. . , (allowable leakage) (abnormal leakag
3、e) . (leak-before-break) (warning) . (spurious alarms) . , (data display) . , (trends) . , . (reactor coolant & associated system) (leakage detection system) , , , , . 2. . , , . KS C IEC 60911: 1987 KS C IEC 60980: 1989 KS C IEC 61225: 2006 IEC Multilingual dictionary: 1992 Electricity, Electronics
4、 and Telecommunications IEC 910: 1998 Containment monitoring instrumentation for early detection of developing deviations from normal operation in light water reactors IAEA Safety Guide 50 SG D9: 1985 Design aspects of radiation protection in nuclear power plants IAEA Safety Guide 50 SG D12: 1985 De
5、sign of the reactor containment systems in nuclear power plants IAEA Safety Guide 50 SG D13: 1986 Reactor coolant and associated systems in nuclear power plants ISA S67.03: 1982 Standard for light water reactor coolant pressure boundary leak detection C IEC 61250: 2006 2 3. . 3.1 (accessible area) (
6、routine function) (health physics procedure) 3.2 (accuracy) (indicated value) (true value) 3.3 (boiling water reactor) 3.4 (calibration) (series of devices) . 3.5 (coolant) (reactor pressure boundary) 3.6 a) b) c) d) e) f) ( .) 3.7 (leak) , 3.8 (leakage) a) b) ( , , .) c) (identified leakage) 4.1 d)
7、 (leakage rate) (20 ) (100 kPa) SI e) (unidentified leakage) 4.1 3.9 (leakage monitoring instrument system) 3.10 (pressurized water reactor) , 3.11 (reactor containment) ( ) 3.12 (reactor coolant associated system) , , , a) b) , C IEC 61250: 2006 3 ( ) (heat sink) (intermediate cooling loop) 1) 2) (
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