1 4 2 OECD 130$/kg 400 1 2001 64,000 60 235 0.7 238 235 3 5 235 238 235 2 1 99 99 ( 4.1.1.1) 60 1 2
MOX MOX MOX 238 3 3
(http://www.fepc.or.jp/menu/nuclear/nuclear8.html ) MOX PUREX 4.1.2.1 3 4cm 4 5 6 4 PUREX TBP n 5 6 PUREX
99.9 % 7100 7 UP3 B205 THORP 1000 100 800 900 800 2005 7 10 4.1.2.1 MOX 50 1 8 IAEA 9 30 50 300m 10 7 8 0.022 msv( ) 1 msv ( 2.4 msv) 9 IAEA International Atomic Energy Agency 7 7-3 10 2000
http://mext-atm.jst.go.jp http://www.jnfl.co.jp
235 238 238 235 3 235 3 5% 235 1% (MOX) MOX 4 9% 235 235 MOX 1960 1980 4.1.3.1 MOX 11,12 2001 12 10 55 3,543 MOX 1,614 1,204 3,436 MOX 1963 BR3 MOX MOX 2001 20 10 3 2 2 37 MOX 1970 MOX 1974 PWR 1987 B PWR MOX 2001 58 90 kw 20 MOX MOX 3 2001 4,000 kwh MOX 10% 1966 BWR MOX 1970 2001 14 PWR 11 12
9 BWR 5 MOX 2001 19 130 kw 10 MOX MOX 50% MOX MOX 1995 3 PWR 2001 7 2 MOX MOX 20% PWR 1978 MOX 1994 2001 5 3 MOX MOX 40% 1980 1990 PWR 1 BWR MOX 2010 16 18 ATR 13 1978 MOX 2003 3 772 MOX 2002 13
U FBR: Fast Breeder Reactor ( ) 99.3% U-238 Pu 3ppb 3mg 10 1951 EBR- NaK U-Pu MOX 12 5 31 2015 FBR FBR FBR U-238 Pu-239 (U) U-235 0.7 99.3 U-238 U 235 0.7 3 5 U-235 2
2.5 2.5 1 U-235 4.2.2.1 U-235 FEPC INFOBASE 2002 2MeV 14 15 U-235 16 U U-238 17 n U-238 U-239 U-239 23.5 18 Np -239 Np-239 2.35 Pu-239 Pu-239 U-235 U-238 U-239 Np-239 Pu-239 U-238 Pu-239 Conversion U-235 Pu-239) C Conversion ratio) C 0.4 0.6 C 14 H O 15 280 0.05eV 16 v v /v 17 U-238 1MeV 18 1 U 92 Np 93 Pu 94 Am 95
Breeding C B Breeding ratio Pu-239 6 Pu 3 Pu 3 5% U-235 1 U-235 1% Pu(Pu-239 Pu-241) Pu 2 4 Pu-239 19 2 20 21 1 1.5 U-235 0.7% 0.5% 0.75% 0.5% 1.5 0.75% 100 3 60% 4.2.2.1 C.00 19 20 C 0.5 TC TC = 1 C C C 1 1 C 2 21 Pu-240 Pu-242 Pu-238 Am-241
U-238 U-235 2.5 U-235 15 2. U-238 4.2.2.2 1 2 C 1 2.5 4.2.2.2-235 2.1 U-235 Pu-239 0.1MeV 2.5 Pu-239 B=1.2 Doubling time 30 30
1/30 22 30 B=1.24 1.29 23 B Pu 3 5% Pu(Pu-239 Pu-241) 2 4 Pu-239 Pu Pu-240 Pu-242 Np Am Cm Tc-99 I-129 92 TRU TRU 24 89 Ac) 103 (Lr) MA MA Pu-U Pu Pu-239 Pu-241 Pu Am Np-237 100% Tc-99 21 I-129 16 22 B B 23 CRBR 24 TRU Np-237 2.14 Am-241 433 Am-243 7.37 Cm-243 Cm-244 Cm-245
MA 4.2.2.3 ( )ALI Bq Th Th-232 U U-238 Pu-239 Th-232 Th-233 2 U-233 4.2.2.2 U-233 2 2 U-233 2 Pu-239 Np-239 Pa-233 Np-239 2 Np-239 2.35 27 Pa-233
Xe-135 He Th U 413 N MSR: Molten Salt Reactor B=1.05 660 U-Pu ADS Pu-239 H O H Na Na Na-23 Na-24 15 12.5 20 0.97 98 400 0.85 100 1/4 881 10 LOCA 40% Na
H2O Na SUS304 SUS316 SCC Na Na ppm Na Na 2 25 1% 13 26 Pu-239 0.21 U-235 (=0.64%) 1/3 27 25 10 10 26 Pu-239 0.21 U-235 (=0.64%) 1/3 U-238 U-235 Pu-241 1/2 27 k
U-238 Na Na 881 Na 600 Na U-235 Pu-239 Pu-241
FBR (NaK) Na Na 23 Na ECCS 40% Na 10ppm 18 Cr-8 Ni Na FBR 4.2.3.1 Na Na Na Na Na H2O O H2 1 Na 2 Na 2 Na 3 4.2.3.2 Na Na 2 Na
4.2.3.3 Na U FBR 2 2 Na
FBR MOX Na Na Na (Pb) (Pb-Bi) Pb Pb-Bi Pb 1700 11 600 Pb 10.3 300 550 Pb 327 Bi 44%-Pb 56%-Bi 125 Bi Po-210 138
HCDA 28 CDA CDA HCDA 100MW Na 600 880 300 DBA Na ULOF 29 Na CDA HCDA 30 BDBA ULOF UTOP 31 ULOF CDA FBR CDA CDA SNR-300 1980 RSK 1991 SNR-300 CDA 28 HCDA: Hypothetical Core Disruptive Accident CDA Core Disruptive Accident 29 ULOF: Unprotected Loss Of Flow 30 BDBA: Beyond DBA 31 Unprotected Transient Over Power
CDA 1957 1960 1967 32 1977 5 kw 14 kw 2 Na 1970 1983 5 1985 1994 4 5 1995 8 29 5 kw 18 Na 1995 12 8 40% A B C 3 2 C 2 Na 0.7 4.2.4.1 Na Na C Na 2 Na C 2 Na 2 C Na Na ( 1.5mm) 32
C Na ( ) 2 A B 4.2.4.2 2 Na SUS304 10mm 22mm R Na Na 3 48 6 42
60 186 22 10 ( mm) 6 42
4.2.4.3 Na 2 Na 0 +1 2 Na Na 4.2.4.4 12 12 8 Na 4.2.4.5
2 Na Na Na 12 12 8 Na Na Na Na 2 2 2
2 Na Na Na Na Na 4.2.4.6 Na 2out of 2 * 2 out of 3 13 1
2003 27 Na 507 Na150m 33 34 1995 0.7m 2 Na NaOH 35 Na 6mm 1.5mm Na 1985 0.22kg/cm 0.6kg/cm G 460 530 Na Na Na 507 Na 460 Na 38mm 1.5m 1.6m 4 35 Na2O2 NaOH O2 2- NaFe
Na m Na 1973 Na 4 Na Na Na Na 5 Na Na SWAT 36 37 4 38 1987 PFR 40 PFR Na Na Na- Na PFR PFR 4.2.5.1 PFR 36 SWAT : Sodium Water Reaction Test Na 37 Na 38
14 2 13 PFR PFR 4 Na- 3 3 4.2.3.2 4.2.3.2
m 2 Na 1 ULOF 3 Na Na 380MJ 500MJ 380MJ 110MJ 2 Na 3 1 1 1
FBR Na 2000 4.2.6.1
12 5 31 MOX Na 1999
1999 2000 39 2001 2005 2015 FBR 2030 Science Technology 1932 1938 CP-1 1942 10 10 1945 1952 NaK FBR 20 1957 18 NY 40 ASME ASME 1973 2 39 PUREX 40 ASME Mechanical Engineering April 1984 1870 1910 41 1 3 1
PFR 20 25 kw 120 kw BN-600 Na BN-800 CEFR FBR 1990 1993 1994 1994 1996 1996 1998 2000
2000 2000 2000 2001 2003 2003
MOX MOX BOR-60 BN-600 DFR PFR SEFOR FFTF KNK- SNR-300 CRBR BN-800 EFR EBR- - DFR MOX MOX MOX 1/10 U Pu UO2 2800 PuO 2 2400 20% 2750 20% 10%Zr 1060 85% 95 97% MOX 1970 80 FBR PUREX MOX PUREX TRU Pu Pu MA MOX ANL RIAR ANL FBR IFR Integral Fast Reactor EBR- FCF Fuel Conditioning Facility EBR- 5 Na
Na MOX N-14 C-14 N-15 PUREX MOX MOX ANL FBR MOX IFR MOX Na
1940 80 EBR-I(1951 ) EBR- (1961 ) FERMI-I(1963 ) FFTF(1980 ) 2001 12 FFTF DOE (NERI) 1999 (GEN-IV) 2000 GEN- AFCI Advanced Fuel Cycle Initiative ( 25 kw ; 1973 ) 1998 11 10 2002 2003 1 7 6 15 (LLFP) ( 124 kw 1985 ) 1998 12 2025 PFR( 25 kw 1974 ) 21 1994 50 60
KNK- KNK- ( 2 kw; 1972 ) SNR-300 32.7 kw 1991 FBR BOR-60( 1.2 kw; 1968 ) BN-600( kw; 1980 ) BN-600 1981 75 BN-800( 80 kw) 2001 2010 BN-600 BN-800 BREST BR-10( 8000kW; 1958 ) 2002 12 BN-350( 75 kwt 35 kwe 15 kwe 20 1972 ) BN-600 1999 ( 6.5 kw, 2.5 kw) 1999 2005 2025 100 kw KALIMER 15 kw 2006 2010 FBTR( 1.5 kw; 1985 ) 1997 7 PFBR( 50 kw) 2009 2003
200 4.3.1.1
4 15 7 15 4.3.1.1 300 300 9 41
16,600 14 12 890 15 8 200 MOX 87,000 10 3 200 81,000 10 3 8,000 10 3 200 500,000 12 3 [ ] http://www.env.go.jp/recycle/index.html 4,500 4 600 12 12 1,051 5,236 http://www.enecho.meti.go.jp/rw/gaiyou4.html
http://www.jnfl.co.jp/
43 40cm 1 1.3m 400 500kg 40 1 6 2002 30 50 300m 4.3.2.1 1 30 4
4.3.2.2 3 12 6 12 10 14 12 40 44 4 100 kw 50 3 44 (http://www.numo.or.jp/)
http://www.enecho.meti.go.jp/rw/hlevel1.html http://www.ocrwm.doe.gov/
(1999) 3 JNC TN1400 99-023, 1999