JAERI 1287 JNDC Nuclear Data Library of Fission Products Fir

More documents

Recommendations

Info

22 JNDC Nuclear Data Library of Fission Products JAERI 1287 and A are given as neutron spectral data in Groups 26 and 27, respectively. The thermal neutron flux 0,* in Eq. (2.6.1) is given as the integral of the neutron flux below 0.5 eV. 4>ih= 4>{E)dE. (2.6.4) Jo 2.7 Nuclear Data Tables The evaluated nuclear data of fission products in the present JNDC FP Nuclear Data Library are tabulated in this section. The decay data and fission yield data are given in Table 2.7.1 for each mass number. The decay chain diagram is shown graphically for each mass number. The branching ratios are given in the decay chain diagram if more than one decay modes exist for some fission product nuclides in the decay chain. The feeding mode through neutron capture is designated by (n,r) and the one through the delayed neutron emission by(d n)in the diagram. When there are the ground and isomeric states in a neutron captured nuclide, the capture cross section must be divided among them. However, there is not enough information about partial capture cross sections. The fractions in the diagram are taken from the ratios of the thermal neutron capture cross sections, which were taken from Table of Isotopes or BNL-325 57 ^. The decay constant {A), Q-value and the average decay energies of beta-rays (Ep), gammarays (Er) and internal conversion electrons (ECE) are given for each nuclide as the decay data in Table 2.7.1 in addition to the decay chain diagram. If there are more than one decay modes for some nuclide, Q-value is averaged with the weight of branching ratio. The average energies Ep, Er and ECE were calculated by the PROFP code 28) using the intensity and energy data. For the nuclide with no or with incomplete experimental data, the necessary decay data had been estimated with the gross theory of beta decay as described in Sec. 2.3. The most of the independent fission yield data have been taken from the compilation by Rider and Meek 41) and supplemented by the present authors for the additional nuclides and isomeric states. Independent yield values are normalized so that the sum of yields is 200% per fission. Then, the cumulative yields have been calculated from the independent yields using the branching ratios in this library as described in Sec. 2.4. Ten sets of different independent and cumulative yields are given in the table for six fissionable nuclides and three neutron energies. The ten sets are: (1) 235 U , t ; t = thermal neutron fission (2) 235 235 TJ > ^ 235 U u ,/'•/ , / = fission spectrum neutron fission 235TJ (3) 235Tj , ^ h \ h = 14 MeV neutron fission (4) (5) (6) (7) (8) (9) (10) 238TJ 238TJ 239pu 239 Pu 241 pu 233 ij , f , t , f , t I Twenty-seven group neutron capture cross sections are given for 80 nuclides in Table 2.7.2. Groups 1 to 25 shown in Table 2.6.1 are for fast reactor calculations. Groups 26 and 27 are for thermal reactor calculations; the resonance integral and the thermal neutron capture cross section for 2200 m/s-neutrons, respectively (cf. Sec. 2.6). The calculation of fission yields, the data edition, the tabulation and the graphical representation of decay-chain diagram have been performed by a computer code PROFP-Y 58) .
ilass No. 66 X l/sec ) O-val uelMeV ) E- beta IMeV ) E-gammo( MaV) E- Z X © o D E -o C 0) TJ C a) D. T> c 1 .C (MeV ) 235U ( J j 23B|J ( F ) 23E U ( H ) u i r ' 238 U ( H ) 238 Pu( T ) 239 Pu( F ) 2 "Pu( T ) 233|J ( J ) 232 Th( F ) 23B U ( T ) 23S|j ( F ) 235 U ( H ) 238|J ( F ) 238 U ( H ) 239 Pu( T ) 239 Pu( F ) 2 " ] Pu( T ) 233 U ( T ) 232 Thl F ) 2.5941E-00 9.8780E*00 3.8630E->00 1 .6330E-t0D 0.0 Z.Z100E-11 4.8400E-I0 2.0200E-06 9.7200E-11 1.4600E-07 1.0S0DE-I1 7.1600E-I1 1.J700E-I0 I.OSOOE-11 4.9600E-09 2-2100E-11 4-8400E-10 2.0200E-08 9.7200E-11 1.4500E-07 1-0600E-11 7.1500E-U 1.170OE-10 1-09D0E-11 4.9600E-09 24C r '25Mn 3.9496E*00 l.«80E*01 4.7390E*00 4.6440E+0D 0.0 Z-37Z1E-09 4.B684E-08 6.1202E-0S 2.0372E-09 J.034BE-0S Z.6108E-09 1.6B71E-DB 7.9370E-09 2.7709E-09 1.1996E-07 2-3600E-Q9 4-5200E-D8 B.1000E-D8 1.94D0E-09 1.0200E-05 2.B000E-09 1.6600E-08 7.820DE-09 2-7600E-D9 1-1600E-07 2BF 6 1.6907E-01 6.0360E-»00 2.2670E->00 1 .047OE->O0 3.3730E*0O 0.0 4.887ZE-08 6.9B68E-07 !.21J2E-04 1.6237E-08 6.2646E-06 S.4711E-08 4.ZZ67E-O7 9.9I37E-08 1.J377E-07 1.0760E-06 4.6500E-OB 5-5O0OE-O7 1 .1500E-04 1.4Z00E-08 S.2300E-05 8-2100E-08 4.0600E-01 9.120OE-O6 1 -1ID0E-07 9.660OE-O7 Table 2.7.1 Decay data and yield data of each fission product nuclide ^Fe- 27CO 2.4889E-0I 9.6630E*00 2.90BOE->00 0.0 7.2972E-08 8.69S8E-07 2.7612E-04 1.79I7E-06 8.3246E-06 1.71D1E-O7 8.4467E-07 I-3134E-07 2.3377E-07 1.20BOE-OB 2.4100E-03 2.6400E-07 l.BBOOE-04 !.6800E-09 2.0600E-05 8.6300E-08 4.2Z00E-07 3.22D0E-O8 1-2000E-07 I.2900E-07 ~^27C 28NI 3-S07IE-06 2.3B00E-01 B.8147E-02 0.0 0.0 7.599ZE-08 8.7988E-07 2.94S2E-04 I-79B9E-08 8.3886E-06 1.881IE-07 9.09B7E-07 I-3368E-07 2-6367E-07 1.2113E-06 3.0ZODE-09 2.OZ00E-O8 1.8400E-05 7.I600E-11 6.4000E-07 1-7I00E-08 6.6000E-06 Z.340DE-09 2.9900E-08 6.3400E-09 0 >2sNf 29CU 2.2652E-03 2.64t6E->00 1.0749E-100 8.4716E-02 0-0 7.6999E-08 8.7993E-07 2.94GEE-04 1-7989E-08 8.3886E-06 I.B820E-07 9.1002E-07 1-3368E-07 2.6384E-07 1.2113E-OB 7.3900E-1Z 4.3300E-11 1.3000E-07 3.17S6E-14 1-0200E-09 9.3700E-11 3.4600E-J0 3.B600E-I2 1.7200E-10 3.2300E-J2 0.0 0.0 0.0 0.0 0-0 3oZn 7.5999E-08 B.7993E-07 2.94GBE-04 1.7989E-08 8-3886E-06 1.8BZ0E-07 9.1002E-07 1.3368E-07 2.6384E-07 1.Z113E-D6 Z.7379E-15 8.9965E-1S 4.8600E-11 3.42S1E-18 8-4193E-14 S.7749E-14 ) .7168E-13 7.6B13E-16 1 .45S7E-13 4.1463E-I6 3lG0 2.0483E-0S 6.17B0E»00 9-73Z4E-01 2.4SOBE-.00 0.0 1 -4984E-20 4.1743E-20 8.1G91E-16 3.1161E-24 2.8344E-19 7.3203E-19 2.1221E-18 2.5433E-21 2.0010E-18 4.4BE0E-22 I.4984E-20 4.1743E-20 8.1690E-16 3.11E1E-24 2.8344E-19 7.3203E-19 2.122JE-I8 2.B433E-21 2.0010E-18 4.4660E-22 —3oZri* 3i Go^ 32G6 3zGe B.482OE-0S Z.1020E*00 6.7308E-02 E.8444E-01 1.3162E-D2 I.0921E-26 1.74S6E-2B E.ZS18E-Z2 6.427SE-3J 4.6020E-Z6 9.3183E-2B 2.0869E-24 1-0109E-27 3.3671E-24 1.074GE-Z8 1.0921E-26 1.7456E-26 B.2518E-22 6.427SE-31 4.5020E-26 9-3183E-25 Z.0B69E-Z4 1.O1O9E-Z7 3.3671E-24 1.0746E-28 50 2! I 3 p. o
Page 1 and 2: oo CNI a: LU JAERI 1287 NEANDC(J)91
Page 3 and 4: JAERI 1287 JNDC Nuclear Data Librar
Page 5 and 6: JAERI 1287 Contents 1. Introduction
Page 7 and 8: JAERI1287 1. Introduction A reliabl
Page 9 and 10: JAERI 1287 2. Nuclear Data Library
Page 11 and 12: JAERI 1287 2. Nuclear Data library
Page 17 and 18: JAERI1287 2. Nuclear Data Library o
Page 21 and 22: JAERI1287 2. Nuclear Data Library o
Page 27: JAERI1287 2. Nuclear Data Library o
Page 31 and 32: Mass 68 X 1/sec ) No. Q-value(V eV
Page 33 and 34: Moss No. 70 X l/sec ) Q-volue(MeV )
Page 35 and 36: Mass No. 72 X ( 1/BBC ) Q-volue(MeV
Page 37 and 38: Moss 74 X 1/sec ) No. Q-voluelMeV )
Page 39 and 40: 1Joss No. 76 X l/sec) Q-value(UeV )
Page 41 and 42: •loss No. 78 X ( 1/BOC ) Q-volue(
Page 43 and 44: Mass No. 80 X l/sec ) Q-valu9(MBV )
Page 45 and 46: dass No, 82 X l/sec ) 0-vo1ue(MeV )
Page 47 and 48: Mass No. 84 X I 1/S8C ) Q- volue(Me
Page 49 and 50: 1/ass No. 86 1/sec ! O-valuelMeV )
Page 51 and 52: Moss 88 X 1/90C ) No. Q-voluelMeV )
Page 53 and 54: X Mass No. 90 0- v a'u e!Me V 1 E-
Page 55 and 56: \ doss No. 92 0- voluelMeV ) £- bs
Page 57 and 58: X doss No. 94 Q- va1uel MBV ) E- be
Page 59 and 60: X tfass No. 96 !/sec ) 0- v o 1 u e
Page 61 and 62: Moss No. 98 *(1/sec ! 0-volue( MSV
Page 63 and 64: Joss 100 X ( I/sec i No.. Q-valuelM
Page 65 and 66: Mass No. 3 02 A ( l/sec I 0-volue(M
Page 67 and 68: Aass No . 104 0- voluelMeV ) c _ be
Page 69 and 70: ^oss No. 106 X I 1/sec ) Q-vo1uelMe
Page 71 and 72: yloss No. 108 ( l/sec ) O-vol uel M
Page 73 and 74: X ilass No. 110 1/sec ) 0- va 1ueI
Page 75 and 76: Moss No. 112 X I/sec ) O-voluelMeV
Page 77 and 78: Mass No. 114 X 1/sec ) Q-volue(MeV
Page 79 and 80:
•loss No. 116 X ( l/sec ) O-value
Page 81 and 82:
Mass No. 118 X : I/sec 1 0- vo!ue(
Page 83 and 84:
Mass 120 No. X I/sec ! 0-va!ue(MeV
Page 85 and 86:
1doss No. 122 X 1/68C ) O-volue!MeV
Page 87 and 88:
X Moss 124 1/sec ) No. 0- vrj 1 uel
Page 89 and 90:
X Moss No. 126 0- voluet MeV ) U-l
Page 91 and 92:
dass No. 128 X ( l/sec ) Q- value!
Page 93 and 94:
Moss No. 130 X ( l/sec ) Q-voluelMe
Page 95 and 96:
kloss No. 132 X ( I/sec ) 0- val us
Page 97 and 98:
X Moss No. 134 1/sec ) 0- voluelMaV
Page 99 and 100:
X 4OES 136 1/sec ) No. O-valuslMaV
Page 101 and 102:
Mass No. 138 X ( l/sec ) O-volue(MB
Page 103 and 104:
Mass No. 140 X ( 1/S8C ) 0- value!
Page 105 and 106:
Mass No. 142 X 1/sec ) Q-valuei MeV
Page 107 and 108:
vioss No. 144 X 1 I/sec ) E- bsta !
Page 109 and 110:
doss No. 146 X ( t/sec ) 0- vol ue(
Page 111 and 112:
Mass No. 148 X( 1/Sec ) 0-vo1ue(UeV
Page 113 and 114:
Mass No. 150 * l/SBC) 0-voluelMeV )
Page 115 and 116:
doss No, 152 X ( l/sec ) Q- voluelU
Page 117 and 118:
Mass No. 154 X 1/sec ) O-valuelMeV
Page 119 and 120:
Moss No. 156 * ( 1/sec 1 Q-volue( M
Page 121 and 122:
Moss No. 158 A ( i/sec ) Q- val ue(
Page 123 and 124:
X Moss No. 160 1/sec ) 0- vo 1 u&(
Page 125 and 126:
X Mass No. 162 0- volue( MeV ) E- b
Page 127 and 128:
Mass No. 164 X ( l/5ec 1 0- value!d
Page 129 and 130:
Mass No. 166 X ( l/sec ) O-value(Me
Page 131 and 132:
doss No. 3 68 X ( l/sec ) 0- volue(
Page 133 and 134:
dass No. 170 X ( 1/sec ) Q- value!M
Page 135 and 136:
Mass No. 172 X 1/sec ) O-value(MBV
Page 137 and 138:
JAERI 1287 2. Nuclear Data Library
Page 139 and 140:
JAERI1287 133 3. Comparison of Calc
Page 141 and 142:
JAERI 1287 3. Comparison of Calcula
Page 143 and 144:
z o 10 to UJ u. O 0. UJ Q a o 0.80
Page 145 and 146:
V) V) UJ o UJ a 0.70 0.60 0.50 0.40
Page 147 and 148:
1 .20 z o — 1 .10 to to UJ UJ o a
Page 149 and 150:
z o UJ 1Z O a. o UJ o o 0.80 0.70 0
Page 151 and 152:
V) X Z o CO UJ r: o Q. a: cc a: 03
Page 153 and 154:
7.00 to 6.00 * 2 O VJ
Page 155 and 156:
UJ 0.80 0.70 0.60 - 0.S0 UJ O 0. CT
Page 157 and 158:
JAERI 1287 151 4. Calculation of De
Page 159 and 160:
JAERI 1287 4. Calculation of Decay
Page 161 and 162:
Page 163 and 164:
Page 165 and 166:
Page 167 and 168:
Page 169 and 170:
Page 171 and 172:
Page 173 and 174:
Page 175 and 176:
Page 177 and 178:
Page 179 and 180:
JAERI1287 4. Calculation of Decay P
Page 181 and 182:
Page 183 and 184:
JAER11287 4. Calculation of Decay P
Page 185 and 186:
Page 187 and 188:
Page 189 and 190:
Page 191 and 192:
Page 193 and 194:
Page 195 and 196:
LU CO CO CO u. v. > LU 3; LU 3 O Q_
Page 197 and 198:
UJ CO ION CO CO LJ_ MEV — UJ O Q_
Page 199 and 200:
(_> UJ to If) to LU a: LJ O o_ >cr
Page 201 and 202:
- LU to ION to to 01 tu 3 O Q_ CE L
Page 203 and 204:
- LU CO ION •FISS LU r: o a 2= ^
Page 205 and 206:
o to > LU O 0- o LU Q OD 10' 10" 10
Page 207 and 208:
o to Hi UJ O 0- o LU D cr x: o + CE
Page 209 and 210:
z: o z: a: UJ o 0. o a: O m 1 10°
Page 211 and 212:
o crc UJ O 0. cr 10" 10" 10 10" 10"
Page 213 and 214:
CO CO UJ r: o Q_ LU a cr I— UJ CD
Page 215 and 216:
CO CO > UJ O UJ D CT O 10' 10" 10 1
Page 217 and 218:
o > UJ o a. UJ o UJ 03 10' - 10 DCH
Page 219 and 220:
to Ll_ LU o LJ CE O LU CD ! 10 1 10
Page 221 and 222:
o to >• LJ o a 0 10' 10" 10' 10'
Page 223 and 224:
JAERI 1287 217 Acknowledgment The a
show all

JAERI 1287 JNDC Nuclear Data Library of Fission Products Fir

Create successful ePaper yourself

Delete template?

Save as template?