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1 PWRPressurized Water Reactor BWRBoiling Water Reactor PWR BWR [ ]
2
3 Defense in Depth
4
5 14
6 Design Basis Accident : DBA RIE: Reactivity Initiated Event LOCA: Loss of Coolant Accident ECCS: Emergency Core Cooling System
7
8 IAEAInternational Atomic Energy Agency IAEA IAEA
9 IAEAInternational Atomic Energy Agency OECD/NEAOrganization of Economy, Cooperation and Development / Nuclear Energy Agency IRS Incident Reporting System
10 IAEA OECD/NEA (International Nuclear Event Scale: INES) INES INES INES (1986 ) 7 TMI2 (1979 ) 5 INES INES
11 INES [ ]
12 10 PSRPeriodic Safety Review PSR) PSR 30 PSR
13 6 (Cu) (P) Mn,Mo,Ni 1%
14 BWR SCC BWR SCC SCC Cr 23C 6 SCC SUS316L SCC SCC 7 8
15 6-3(6) 9 5 SCC µ µ [ ] JAERI-Conf , (2003) 9
16
17 (IAEA: International Atomic Energy Agency) INSAG: International Nuclear Safety Advisory Group INSAG INSAG IAEA INSAG INSAG-12 INSAG IAEA INSAG, "Basic Safety Principles for Nuclear Power Plants," Safety Series No. 75-INSAG-3, (1988). 12 IAEA INSAG, "Safety Culture," Safety Series No. 75-INSAG-4, (1991). 13 IAEA, Developing Safety Culture in Nuclear Activities - Practical Suggestions to Assist Progress, Safety Report Series No.11, (1998).
18 10 BNFL MOX NS Questioning Attitude 14 NS NSP-RP NS
19 IAEA INSAG, "Safety Culture," Safety Series No. 75-INSAG-4, (1991) B&W PWR 95.9 kw 97% 2/3 93PBq 0.56TBq 1mSv (ECCS)
20 km 13 5 WANO Vol.44, No.2 (2002)
21 kg m 3 10km
22
23 Big Thomson ( Tel:
24 EU ExternE 23 (Years of Life Lost: YOLL) 24 NOx SOx BWR2 PWR3 BWR ExternE (EU) externality ( 24 A. Strupczewski, "Comparative Assessments of Emission from Energy Systems, Benefits and Burdens", IAEA Bulletin, Vol.41 No.1,(1999). 25 USNRC, "Severe Accident risks: An Assessment for Five U.S. Nuclear Power Plants," NUREG-1150, (1990).
25 (1)(2)(3)
26 IAEA Bulletin, Vol.41, Nr.1, (1999) * 211
27 Probabilistic Safety AssessmentPSA PSA PSA 26
28 PSA PSA 4 12 PSA PSA PSA PSA ( ) ( Tel: (
29 TMI (1)
30 (2) (3)
31
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