PWRPressurized Water Reactor BWRBoiling Water Reactor 2 1.3.1 1.3.2 PWR 1 2 2 BWR 6.1.1 [ ] 2002-2003

6.1.2 1 2 3

http://www.atom.meti.go.jp/ 4 6.1.3 1 4 Defense in Depth

http://www.atom.meti.go.jp/ 1 2 6.2.1

14

Design Basis Accident : DBA RIE: Reactivity Initiated Event LOCA: Loss of Coolant Accident ECCS: Emergency Core Cooling System

15 2 12 9 14 10 15 8 11 9 30 11 12 24

15 6 30 6.3.1 12 IAEAInternational Atomic Energy Agency 5 5 1986 1991 IAEA IAEA 1996 10 24

13 6.3.2 IAEAInternational Atomic Energy Agency OECD/NEAOrganization of Economy, Cooperation and Development / Nuclear Energy Agency IRS Incident Reporting System

http://www.atom.meti.go.jp/ 1990 IAEA OECD/NEA (International Nuclear Event Scale: INES) 2 1992 3 INES 6.3.1 0 7 3 3 1 3 4 7 INES INES (1986 ) 7 TMI2 (1979 ) 5 INES 1999 4 INES

2000 6 2 5 4 INES [ ] http://nsdel.tokai.jaeri.go.jp/ines/

10 PSRPeriodic Safety Review 6.3.3 8 4 8 4 http://www.atom.meti.go.jp/ 1. PSR)10 1 2. PSR 30 PSR 10 3. 4.

6 (Cu) (P) 1997 2000 2002 2003 6 Mn,Mo,Ni 1%

BWR 7 8 6.3.4 SCC 1970-1980 BWR SCC SCC Cr 23C 6 SCC 0.02 0.03 SUS316L SCC SCC 7 8

6-3(6) 9 5 SCC µ µ [ ] 2003 3 17 JAERI-Conf 2003-014, (2003) 9

9 10 10 12 14 10 17 15 4 24

14 12 19 (IAEA: International Atomic Energy Agency) INSAG: International Nuclear Safety Advisory Group 10 11 12 6.4.1 INSAG 13 1 2 3 10 INSAG IAEA 1985 1996 INSAG-10 1999 INSAG-12 INSAG-15 11 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).

10 BNFL MOX 11 14 11 9 NS 36 15 14 10 17 16 Questioning Attitude 14 NS NSP-RP-0092001 2 20 15 NS http://www.nsnet.gr.jp/. 16 14 10 17

IAEA INSAG, "Safety Culture," Safety Series No. 75-INSAG-4, (1991) 17 1979 3 28 2 B&W PWR 95.9 kw 97% 2/3 93PBq 0.56TBq 1mSv (ECCS) 17 56 56 12

52 18 1986 4 26 4 31 30km 13 5 WANO 18 15 Vol.44, No.2 (2002)

19 1999 9 30 2 18.8 2.4kg 10 35 20 10 1 8 50 350m 3 10km 10 30 10 2 6 30 10 1 4 30 20 1995 12 8 2 19 11 20 9

21 1997 3 11 10 21 9

22 1985 520 1986 705 1991 59 1984 2000 1988 160 1989 645 1976 Big Thomson 144 1986 31 1999 22 2002 10 5 (http://nsc.jst.go.jp/) 3-1-1Tel:03-5253-2111

2 400 6.5.1 EU ExternE 23 (Years of Life Lost: YOLL) 24 NOx SOx 1990 6-6 6.5.2 25 BWR2 PWR3 BWR 1 1 23 ExternE (EU) externality (http://www.externe.info/) 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).

1 2 1 1 1 1 (1)(2)(3)

IAEA Bulletin, Vol.41, Nr.1, (1999) * 211

1993 1997 Probabilistic Safety AssessmentPSA PSA 6.6.1 PSA 26 http://www.mhlw.go.jp/toukei/saikin/hw/life/life00/index.html.

PSA PSA 4 12 PSA 1 1 10 1 100 1 10 1 PSA PSA PSA 1986 1000 1 ( ) 12 27 14 28 27 2002 10 5 (http://nsc.jst.go.jp/) 3-1-1Tel:03-5253-2111 28 14 10 17 (http://nsc.jst.go.jp/anzen/sonota/nscnews_kettei_f.htm)

11 9 11 12 6 12 5 29 29 TMI 55 6 12 5 (1)

12 6 6.7.1 21 12 13 14 (2) (3)

13 14 4