日本原子力学会崩壊熱推奨値の表
「原子炉崩壊熱基準」研究専門委員会: 「原子炉崩壊熱とその推奨値」(社)日本原子力学会(1989 年 8 月) |
「原子炉崩壊熱基準」研究専門委員会: 「崩壊熱の推奨値とその使用法」(社)日本原子力学会(1990 年 7 月) |
Table 8
Tabular Data for Recommended Decay Heat Power for
Fast Fission of 238U and for Irradiation of 1013 Seconds
|
Time | Beta | Uncertainty | Gamma | Uncertainty | Total | Uncertainty |
(s) | (MeV/fission) | (%) | (MeV/fission) | (%) | (MeV/fission) | (%) |
|
0.0 | 8.307E+0 | 2.7 | 7.819E+0 | 3.5 | 1.613E+1 | 2.2 |
1.0E-1 | 8.162E+0 | 2.2 | 7.712E+0 | 3.0 | 1.587E+1 | 1.7 |
1.5E-1 | 8.096E+0 | 2.1 | 7.663E+0 | 2.9 | 1.576E+1 | 1.7 |
2.0E-1 | 8.032E+0 | 2.1 | 7.615E+0 | 2.8 | 1.565E+1 | 1.6 |
3.0E-1 | 7.912E+0 | 2.0 | 7.527E+0 | 2.7 | 1.544E+1 | 1.6 |
4.0E-1 | 7.802E+0 | 2.0 | 7.445E+0 | 2.6 | 1.525E+1 | 1.6 |
5.0E-1 | 7.699E+0 | 2.0 | 7.369E+0 | 2.6 | 1.507E+1 | 1.5 |
6.0E-1 | 7.603E+0 | 2.0 | 7.297E+0 | 2.6 | 1.490E+1 | 1.5 |
8.0E-1 | 7.427E+0 | 1.9 | 7.167E+0 | 2.5 | 1.459E+1 | 1.5 |
1.0E+0 | 7.269E+0 | 1.9 | 7.050E+0 | 2.4 | 1.432E+1 | 1.5 |
1.5E+0 | 6.931E+0 | 1.9 | 6.801E+0 | 2.3 | 1.373E+1 | 1.4 |
2.0E+0 | 6.653E+0 | 1.9 | 6.597E+0 | 2.2 | 1.325E+1 | 1.4 |
3.0E+0 | 6.213E+0 | 1.9 | 6.275E+0 | 2.1 | 1.249E+1 | 1.4 |
4.0E+0 | 5.875E+0 | 1.9 | 6.028E+0 | 2.0 | 1.190E+1 | 1.3 |
5.0E+0 | 5.606E+0 | 1.9 | 5.831E+0 | 1.9 | 1.144E+1 | 1.3 |
6.0E+0 | 5.385E+0 | 1.9 | 5.668E+0 | 1.9 | 1.105E+1 | 1.3 |
8.0E+0 | 5.040E+0 | 1.9 | 5.412E+0 | 1.8 | 1.045E+1 | 1.2 |
1.0E+1 | 4.782E+0 | 1.9 | 5.216E+0 | 1.7 | 9.998E+0 | 1.2 |
1.5E+1 | 4.345E+0 | 1.8 | 4.871E+0 | 1.6 | 9.216E+0 | 1.2 |
2.0E+1 | 4.062E+0 | 1.8 | 4.635E+0 | 1.6 | 8.697E+0 | 1.2 |
3.0E+1 | 3.701E+0 | 1.8 | 4.312E+0 | 1.5 | 8.012E+0 | 1.1 |
4.0E+1 | 3.464E+0 | 1.8 | 4.086E+0 | 1.4 | 7.550E+0 | 1.1 |
5.0E+1 | 3.289E+0 | 1.7 | 3.912E+0 | 1.4 | 7.201E+0 | 1.1 |
6.0E+1 | 3.150E+0 | 1.7 | 3.769E+0 | 1.3 | 6.919E+0 | 1.1 |
8.0E+1 | 2.939E+0 | 1.7 | 3.546E+0 | 1.3 | 6.485E+0 | 1.0 |
1.0E+2 | 2.783E+0 | 1.8 | 3.376E+0 | 1.2 | 6.160E+0 | 1.0 |
1.5E+2 | 2.522E+0 | 1.8 | 3.084E+0 | 1.2 | 5.607E+0 | 1.1 |
2.0E+2 | 2.356E+0 | 1.8 | 2.894E+0 | 1.2 | 5.250E+0 | 1.1 |
3.0E+2 | 2.146E+0 | 1.8 | 2.652E+0 | 1.2 | 4.798E+0 | 1.1 |
4.0E+2 | 2.009E+0 | 1.8 | 2.496E+0 | 1.2 | 4.505E+0 | 1.1 |
5.0E+2 | 1.907E+0 | 1.8 | 2.382E+0 | 1.2 | 4.289E+0 | 1.1 |
6.0E+2 | 1.825E+0 | 1.8 | 2.291E+0 | 1.3 | 4.117E+0 | 1.1 |
8.0E+2 | 1.698E+0 | 1.7 | 2.149E+0 | 1.3 | 3.847E+0 | 1.0 |
1.0E+3 | 1.600E+0 | 1.7 | 2.037E+0 | 1.3 | 3.638E+0 | 1.0 |
1.5E+3 | 1.425E+0 | 1.6 | 1.832E+0 | 1.3 | 3.257E+0 | 1.0 |
2.0E+3 | 1.305E+0 | 1.6 | 1.684E+0 | 1.3 | 2.989E+0 | 1.0 |
3.0E+3 | 1.151E+0 | 1.6 | 1.481E+0 | 1.4 | 2.631E+0 | 1.0 |
4.0E+3 | 1.056E+0 | 1.6 | 1.344E+0 | 1.3 | 2.400E+0 | 1.0 |
5.0E+3 | 9.906E-1 | 1.7 | 1.244E+0 | 1.3 | 2.235E+0 | 1.0 |
6.0E+3 | 9.427E-1 | 1.7 | 1.168E+0 | 1.3 | 2.110E+0 | 1.0 |
8.0E+3 | 8.745E-1 | 1.7 | 1.055E+0 | 1.2 | 1.930E+0 | 1.0 |
|
Table 8 (continued)
Tabular Data for Recommended Decay Heat Power for
Fast Fission of 238U and for Irradiation of 1013 Seconds
|
Time | Beta | Uncertainty | Gamma | Uncertainty | Total | Uncertainty |
(s) | (MeV/fission) | (%) | (MeV/fission) | (%) | (MeV/fission) | (%) |
|
1.0E+4 | 8.263E-1 | 1.7 | 9.760E-1 | 1.2 | 1.802E+0 | 1.0 |
1.5E+4 | 7.447E-1 | 1.7 | 8.529E-1 | 1.2 | 1.598E+0 | 1.0 |
2.0E+4 | 6.897E-1 | 1.7 | 7.824E-1 | 1.2 | 1.472E+0 | 1.0 |
3.0E+4 | 6.147E-1 | 1.7 | 7.011E-1 | 1.2 | 1.316E+0 | 1.0 |
4.0E+4 | 5.636E-1 | 1.7 | 6.509E-1 | 1.2 | 1.215E+0 | 1.0 |
5.0E+4 | 5.260E-1 | 1.7 | 6.142E-1 | 1.2 | 1.140E+0 | 1.0 |
6.0E+4 | 4.973E-1 | 1.6 | 5.855E-1 | 1.2 | 1.083E+0 | 1.0 |
8.0E+4 | 4.564E-1 | 1.6 | 5.425E-1 | 1.2 | 9.989E-1 | 1.0 |
1.0E+5 | 4.285E-1 | 1.6 | 5.112E-1 | 1.2 | 9.397E-1 | 1.0 |
1.5E+5 | 3.857E-1 | 1.6 | 4.589E-1 | 1.2 | 8.446E-1 | 1.0 |
2.0E+5 | 3.606E-1 | 1.5 | 4.249E-1 | 1.2 | 7.855E-1 | 1.0 |
3.0E+5 | 3.308E-1 | 1.4 | 3.801E-1 | 1.2 | 7.109E-1 | 0.9 |
4.0E+5 | 3.123E-1 | 1.3 | 3.491E-1 | 1.2 | 6.614E-1 | 0.9 |
5.0E+5 | 2.987E-1 | 1.3 | 3.250E-1 | 1.2 | 6.237E-1 | 0.9 |
6.0E+5 | 2.878E-1 | 1.2 | 3.052E-1 | 1.3 | 5.930E-1 | 0.9 |
8.0E+5 | 2.710E-1 | 1.1 | 2.740E-1 | 1.3 | 5.451E-1 | 0.9 |
1.0E+6 | 2.582E-1 | 1.0 | 2.503E-1 | 1.3 | 5.085E-1 | 0.8 |
1.5E+6 | 2.356E-1 | 0.9 | 2.093E-1 | 1.4 | 4.449E-1 | 0.8 |
2.0E+6 | 2.199E-1 | 0.9 | 1.824E-1 | 1.5 | 4.023E-1 | 0.8 |
3.0E+6 | 1.986E-1 | 0.8 | 1.480E-1 | 1.6 | 3.466E-1 | 0.8 |
4.0E+6 | 1.844E-1 | 0.9 | 1.266E-1 | 1.6 | 3.110E-1 | 0.8 |
5.0E+6 | 1.740E-1 | 0.9 | 1.121E-1 | 1.6 | 2.861E-1 | 0.8 |
6.0E+6 | 1.659E-1 | 0.9 | 1.015E-1 | 1.5 | 2.674E-1 | 0.8 |
8.0E+6 | 1.536E-1 | 0.9 | 8.657E-2 | 1.4 | 2.402E-1 | 0.8 |
1.0E+7 | 1.443E-1 | 0.9 | 7.601E-2 | 1.3 | 2.203E-1 | 0.8 |
1.5E+7 | 1.277E-1 | 1.0 | 5.907E-2 | 1.2 | 1.868E-1 | 0.8 |
2.0E+7 | 1.162E-1 | 1.0 | 4.967E-2 | 1.1 | 1.659E-1 | 0.8 |
3.0E+7 | 1.003E-1 | 1.0 | 4.124E-2 | 1.2 | 1.416E-1 | 0.8 |
4.0E+7 | 8.930E-2 | 1.1 | 3.818E-2 | 1.3 | 1.275E-1 | 0.8 |
5.0E+7 | 8.098E-2 | 1.1 | 3.676E-2 | 1.3 | 1.177E-1 | 0.9 |
6.0E+7 | 7.453E-2 | 1.1 | 3.588E-2 | 1.4 | 1.104E-1 | 0.9 |
8.0E+7 | 6.543E-2 | 1.2 | 3.468E-2 | 1.4 | 1.001E-1 | 0.9 |
1.0E+8 | 5.963E-2 | 1.3 | 3.378E-2 | 1.4 | 9.341E-2 | 1.0 |
1.5E+8 | 5.218E-2 | 1.4 | 3.213E-2 | 1.5 | 8.431E-2 | 1.1 |
2.0E+8 | 4.872E-2 | 1.5 | 3.086E-2 | 1.5 | 7.958E-2 | 1.1 |
3.0E+8 | 4.471E-2 | 1.6 | 2.869E-2 | 1.6 | 7.340E-2 | 1.1 |
4.0E+8 | 4.160E-2 | 1.6 | 2.674E-2 | 1.6 | 6.834E-2 | 1.2 |
5.0E+8 | 3.881E-2 | 1.7 | 2.494E-2 | 1.7 | 6.375E-2 | 1.2 |
6.0E+8 | 3.626E-2 | 1.8 | 2.327E-2 | 1.8 | 5.953E-2 | 1.3 |
8.0E+8 | 3.172E-2 | 2.0 | 2.029E-2 | 2.0 | 5.200E-2 | 1.5 |
|
Table 8 (continued)
Tabular Data for Recommended Decay Heat Power for
Fast Fission of 238U and for Irradiation of 1013 Seconds
|
Time | Beta | Uncertainty | Gamma | Uncertainty | Total | Uncertainty |
(s) | (MeV/fission) | (%) | (MeV/fission) | (%) | (MeV/fission) | (%) |
|
1.0E+9 | 2.783E-2 | 2.2 | 1.770E-2 | 2.2 | 4.554E-2 | 1.6 |
1.5E+9 | 2.036E-2 | 2.3 | 1.268E-2 | 2.8 | 3.304E-2 | 1.8 |
2.0E+9 | 1.525E-2 | 2.5 | 9.194E-3 | 3.4 | 2.444E-2 | 2.0 |
3.0E+9 | 9.360E-3 | 2.8 | 5.084E-3 | 4.6 | 1.444E-2 | 2.3 |
4.0E+9 | 6.594E-3 | 3.1 | 3.100E-3 | 5.8 | 9.694E-3 | 2.7 |
5.0E+9 | 5.292E-3 | 3.4 | 2.142E-3 | 7.0 | 7.434E-3 | 3.0 |
6.0E+9 | 4.677E-3 | 3.6 | 1.679E-3 | 8.2 | 6.356E-3 | 3.4 |
8.0E+9 | 4.245E-3 | 4.2 | 1.347E-3 | 10.6 | 5.592E-3 | 4.1 |
1.0E+10 | 4.144E-3 | 4.8 | 1.269E-3 | 13.0 | 5.413E-3 | 4.8 |
1.5E+10 | 4.106E-3 | 4.8 | 1.245E-3 | 13.0 | 5.351E-3 | 4.8 |
2.0E+10 | 4.101E-3 | 4.8 | 1.243E-3 | 13.0 | 5.344E-3 | 4.8 |
3.0E+10 | 4.095E-3 | 4.8 | 1.240E-3 | 13.0 | 5.336E-3 | 4.8 |
4.0E+10 | 4.091E-3 | 4.8 | 1.238E-3 | 13.0 | 5.329E-3 | 4.8 |
5.0E+10 | 4.087E-3 | 4.8 | 1.235E-3 | 13.1 | 5.322E-3 | 4.7 |
6.0E+10 | 4.083E-3 | 4.8 | 1.232E-3 | 13.1 | 5.315E-3 | 4.7 |
8.0E+10 | 4.074E-3 | 4.8 | 1.227E-3 | 13.1 | 5.301E-3 | 4.7 |
1.0E+11 | 4.066E-3 | 4.8 | 1.221E-3 | 13.1 | 5.287E-3 | 4.7 |
1.5E+11 | 4.045E-3 | 4.8 | 1.208E-3 | 13.1 | 5.253E-3 | 4.7 |
2.0E+11 | 4.024E-3 | 4.8 | 1.195E-3 | 13.1 | 5.219E-3 | 4.7 |
3.0E+11 | 3.984E-3 | 4.7 | 1.169E-3 | 13.1 | 5.152E-3 | 4.6 |
4.0E+11 | 3.943E-3 | 4.7 | 1.143E-3 | 13.1 | 5.087E-3 | 4.6 |
5.0E+11 | 3.903E-3 | 4.7 | 1.119E-3 | 13.0 | 5.022E-3 | 4.6 |
6.0E+11 | 3.864E-3 | 4.6 | 1.094E-3 | 13.0 | 4.958E-3 | 4.5 |
8.0E+11 | 3.787E-3 | 4.6 | 1.047E-3 | 13.0 | 4.834E-3 | 4.5 |
1.0E+12 | 3.711E-3 | 4.6 | 1.002E-3 | 13.0 | 4.714E-3 | 4.5 |
1.5E+12 | 3.531E-3 | 4.5 | 8.979E-4 | 13.6 | 4.429E-3 | 4.4 |
2.0E+12 | 3.362E-3 | 4.4 | 8.045E-4 | 14.3 | 4.167E-3 | 4.3 |
3.0E+12 | 3.054E-3 | 4.2 | 6.458E-4 | 15.6 | 3.700E-3 | 4.2 |
4.0E+12 | 2.781E-3 | 4.0 | 5.185E-4 | 16.8 | 3.300E-3 | 4.0 |
5.0E+12 | 2.539E-3 | 3.8 | 4.162E-4 | 18.1 | 2.955E-3 | 3.9 |
6.0E+12 | 2.324E-3 | 3.6 | 3.342E-4 | 19.4 | 2.658E-3 | 3.7 |
8.0E+12 | 1.960E-3 | 3.2 | 2.154E-4 | 21.9 | 2.176E-3 | 3.4 |
1.0E+13 | 1.670E-3 | 2.8 | 1.389E-4 | 24.5 | 1.809E-3 | 3.1 |
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