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 6
Tabular Data for Recommended Decay Heat Power for
Thermal Fission of 235U and for Irradiation of 1013 Seconds
|
Time | Beta | Uncertainty | Gamma | Uncertainty | Total | Uncertainty |
(s) | (MeV/fission) | (%) | (MeV/fission) | (%) | (MeV/fission) | (%) |
|
0.0 | 6.509E+0 | 3.0 | 6.438E+0 | 3.1 | 1.295E+1 | 2.3 |
1.0E-1 | 6.436E+0 | 2.5 | 6.384E+0 | 2.6 | 1.282E+1 | 1.8 |
1.5E-1 | 6.401E+0 | 2.4 | 6.349E+0 | 2.4 | 1.275E+1 | 1.7 |
2.0E-1 | 6.368E+0 | 2.4 | 6.328E+0 | 2.4 | 1.270E+1 | 1.6 |
3.0E-1 | 6.305E+0 | 2.3 | 6.279E+0 | 2.3 | 1.258E+1 | 1.6 |
4.0E-1 | 6.247E+0 | 2.2 | 6.233E+0 | 2.2 | 1.248E+1 | 1.5 |
5.0E-1 | 6.192E+0 | 2.2 | 6.190E+0 | 2.1 | 1.238E+1 | 1.5 |
6.0E-1 | 6.140E+0 | 2.2 | 6.150E+0 | 2.1 | 1.229E+1 | 1.5 |
8.0E-1 | 6.043E+0 | 2.1 | 6.075E+0 | 2.0 | 1.212E+1 | 1.4 |
1.0E+0 | 5.956E+0 | 2.1 | 6.008E+0 | 1.9 | 1.196E+1 | 1.4 |
1.5E+0 | 5.766E+0 | 2.0 | 5.862E+0 | 1.8 | 1.163E+1 | 1.4 |
2.0E+0 | 5.605E+0 | 2.0 | 5.740E+0 | 1.7 | 1.135E+1 | 1.3 |
3.0E+0 | 5.343E+0 | 2.0 | 5.544E+0 | 1.6 | 1.089E+1 | 1.3 |
4.0E+0 | 5.135E+0 | 1.9 | 5.389E+0 | 1.5 | 1.052E+1 | 1.2 |
5.0E+0 | 4.963E+0 | 1.9 | 5.262E+0 | 1.5 | 1.022E+1 | 1.2 |
6.0E+0 | 4.817E+0 | 1.9 | 5.154E+0 | 1.4 | 9.971E+0 | 1.2 |
8.0E+0 | 4.583E+0 | 1.9 | 4.979E+0 | 1.4 | 9.561E+0 | 1.1 |
1.0E+1 | 4.400E+0 | 1.8 | 4.839E+0 | 1.3 | 9.239E+0 | 1.1 |
1.5E+1 | 4.074E+0 | 1.8 | 4.582E+0 | 1.2 | 8.657E+0 | 1.1 |
2.0E+1 | 3.855E+0 | 1.7 | 4.398E+0 | 1.2 | 8.252E+0 | 1.0 |
3.0E+1 | 3.563E+0 | 1.7 | 4.134E+0 | 1.1 | 7.697E+0 | 1.0 |
4.0E+1 | 3.367E+0 | 1.6 | 3.945E+0 | 1.1 | 7.312E+0 | 1.0 |
5.0E+1 | 3.220E+0 | 1.6 | 3.797E+0 | 1.1 | 7.017E+0 | 0.9 |
6.0E+1 | 3.102E+0 | 1.6 | 3.675E+0 | 1.1 | 6.777E+0 | 0.9 |
8.0E+1 | 2.922E+0 | 1.5 | 3.482E+0 | 1.1 | 6.404E+0 | 0.9 |
1.0E+2 | 2.788E+0 | 1.5 | 3.334E+0 | 1.1 | 6.123E+0 | 0.9 |
1.5E+2 | 2.563E+0 | 1.6 | 3.076E+0 | 1.1 | 5.639E+0 | 0.9 |
2.0E+2 | 2.417E+0 | 1.6 | 2.906E+0 | 1.1 | 5.323E+0 | 0.9 |
3.0E+2 | 2.229E+0 | 1.6 | 2.686E+0 | 1.1 | 4.915E+0 | 0.9 |
4.0E+2 | 2.103E+0 | 1.6 | 2.541E+0 | 1.1 | 4.644E+0 | 0.9 |
5.0E+2 | 2.007E+0 | 1.6 | 2.432E+0 | 1.1 | 4.439E+0 | 0.9 |
6.0E+2 | 1.930E+0 | 1.5 | 2.343E+0 | 1.1 | 4.273E+0 | 0.9 |
8.0E+2 | 1.808E+0 | 1.5 | 2.203E+0 | 1.1 | 4.012E+0 | 0.9 |
1.0E+3 | 1.714E+0 | 1.4 | 2.093E+0 | 1.1 | 3.807E+0 | 0.9 |
1.5E+3 | 1.543E+0 | 1.4 | 1.888E+0 | 1.2 | 3.431E+0 | 0.9 |
2.0E+3 | 1.425E+0 | 1.4 | 1.740E+0 | 1.2 | 3.165E+0 | 0.9 |
3.0E+3 | 1.269E+0 | 1.4 | 1.534E+0 | 1.2 | 2.804E+0 | 0.9 |
4.0E+3 | 1.171E+0 | 1.4 | 1.394E+0 | 1.1 | 2.565E+0 | 0.9 |
5.0E+3 | 1.102E+0 | 1.4 | 1.289E+0 | 1.1 | 2.392E+0 | 0.9 |
6.0E+3 | 1.051E+0 | 1.4 | 1.208E+0 | 1.1 | 2.259E+0 | 0.9 |
8.0E+3 | 9.753E-1 | 1.4 | 1.088E+0 | 1.0 | 2.064E+0 | 0.9 |
|
Table 6 (continued)
Tabular Data for Recommended Decay Heat Power for
Thermal Fission of 235U and for Irradiation of 1013 Seconds
|
Time | Beta | Uncertainty | Gamma | Uncertainty | Total | Uncertainty |
(s) | (MeV/fission) | (%) | (MeV/fission) | (%) | (MeV/fission) | (%) |
|
1.0E+4 | 9.208E-1 | 1.4 | 1.003E+0 | 0.9 | 1.924E+0 | 0.8 |
1.5E+4 | 8.268E-1 | 1.4 | 8.699E-1 | 0.9 | 1.697E+0 | 0.8 |
2.0E+4 | 7.626E-1 | 1.4 | 7.928E-1 | 0.8 | 1.555E+0 | 0.8 |
3.0E+4 | 6.751E-1 | 1.4 | 7.042E-1 | 0.8 | 1.379E+0 | 0.8 |
4.0E+4 | 6.160E-1 | 1.4 | 6.505E-1 | 0.9 | 1.267E+0 | 0.8 |
5.0E+4 | 5.732E-1 | 1.4 | 6.121E-1 | 0.9 | 1.185E+0 | 0.8 |
6.0E+4 | 5.409E-1 | 1.4 | 5.825E-1 | 0.9 | 1.123E+0 | 0.8 |
8.0E+4 | 4.957E-1 | 1.4 | 5.385E-1 | 0.9 | 1.034E+0 | 0.8 |
1.0E+5 | 4.656E-1 | 1.4 | 5.067E-1 | 0.9 | 9.723E-1 | 0.8 |
1.5E+5 | 4.204E-1 | 1.3 | 4.544E-1 | 0.9 | 8.748E-1 | 0.8 |
2.0E+5 | 3.946E-1 | 1.3 | 4.212E-1 | 0.9 | 8.158E-1 | 0.8 |
3.0E+5 | 3.649E-1 | 1.2 | 3.785E-1 | 0.8 | 7.433E-1 | 0.7 |
4.0E+5 | 3.466E-1 | 1.1 | 3.495E-1 | 0.8 | 6.961E-1 | 0.7 |
5.0E+5 | 3.331E-1 | 1.1 | 3.271E-1 | 0.8 | 6.602E-1 | 0.7 |
6.0E+5 | 3.223E-1 | 1.0 | 3.087E-1 | 0.8 | 6.309E-1 | 0.7 |
8.0E+5 | 3.052E-1 | 0.9 | 2.792E-1 | 0.9 | 5.845E-1 | 0.6 |
1.0E+6 | 2.920E-1 | 0.8 | 2.565E-1 | 0.9 | 5.485E-1 | 0.6 |
1.5E+6 | 2.677E-1 | 0.7 | 2.164E-1 | 0.9 | 4.841E-1 | 0.6 |
2.0E+6 | 2.505E-1 | 0.7 | 1.896E-1 | 1.0 | 4.401E-1 | 0.6 |
3.0E+6 | 2.265E-1 | 0.6 | 1.548E-1 | 1.1 | 3.813E-1 | 0.6 |
4.0E+6 | 2.102E-1 | 0.6 | 1.332E-1 | 1.2 | 3.434E-1 | 0.6 |
5.0E+6 | 1.982E-1 | 0.6 | 1.183E-1 | 1.3 | 3.166E-1 | 0.6 |
6.0E+6 | 1.888E-1 | 0.7 | 1.073E-1 | 1.3 | 2.962E-1 | 0.6 |
8.0E+6 | 1.746E-1 | 0.7 | 9.152E-2 | 1.2 | 2.662E-1 | 0.6 |
1.0E+7 | 1.641E-1 | 0.7 | 8.005E-2 | 1.2 | 2.441E-1 | 0.6 |
1.5E+7 | 1.459E-1 | 0.7 | 6.104E-2 | 1.1 | 2.069E-1 | 0.6 |
2.0E+7 | 1.340E-1 | 0.7 | 5.024E-2 | 1.1 | 1.843E-1 | 0.6 |
3.0E+7 | 1.191E-1 | 0.8 | 4.066E-2 | 1.1 | 1.597E-1 | 0.6 |
4.0E+7 | 1.094E-1 | 0.8 | 3.746E-2 | 1.2 | 1.468E-1 | 0.6 |
5.0E+7 | 1.023E-1 | 0.8 | 3.620E-2 | 1.2 | 1.385E-1 | 0.7 |
6.0E+7 | 9.688E-2 | 0.9 | 3.553E-2 | 1.2 | 1.324E-1 | 0.7 |
8.0E+7 | 8.931E-2 | 0.9 | 3.467E-2 | 1.3 | 1.240E-1 | 0.7 |
1.0E+8 | 8.444E-2 | 0.9 | 3.401E-2 | 1.3 | 1.184E-1 | 0.8 |
1.5E+8 | 7.773E-2 | 1.0 | 3.265E-2 | 1.3 | 1.104E-1 | 0.8 |
2.0E+8 | 7.393E-2 | 1.0 | 3.147E-2 | 1.3 | 1.054E-1 | 0.8 |
3.0E+8 | 6.834E-2 | 1.1 | 2.930E-2 | 1.4 | 9.764E-2 | 0.9 |
4.0E+8 | 6.351E-2 | 1.2 | 2.731E-2 | 1.4 | 9.082E-2 | 0.9 |
5.0E+8 | 5.909E-2 | 1.3 | 2.547E-2 | 1.5 | 8.455E-2 | 1.0 |
6.0E+8 | 5.501E-2 | 1.4 | 2.375E-2 | 1.6 | 7.877E-2 | 1.1 |
8.0E+8 | 4.777E-2 | 1.6 | 2.068E-2 | 1.7 | 6.845E-2 | 1.3 |
|
Table 6 (continued)
Tabular Data for Recommended Decay Heat Power for
Thermal Fission of 235U and for Irradiation of 1013 Seconds
|
Time | Beta | Uncertainty | Gamma | Uncertainty | Total | Uncertainty |
(s) | (MeV/fission) | (%) | (MeV/fission) | (%) | (MeV/fission) | (%) |
|
1.0E+9 | 4.157E-2 | 1.8 | 1.802E-2 | 1.7 | 5.960E-2 | 1.4 |
1.5E+9 | 2.967E-2 | 1.9 | 1.286E-2 | 1.8 | 4.253E-2 | 1.5 |
2.0E+9 | 2.156E-2 | 2.0 | 9.265E-3 | 2.9 | 3.082E-2 | 1.7 |
3.0E+9 | 1.224E-2 | 2.3 | 5.036E-3 | 4.0 | 1.728E-2 | 2.0 |
4.0E+9 | 7.897E-3 | 2.5 | 2.993E-3 | 5.2 | 1.089E-2 | 2.3 |
5.0E+9 | 5.866E-3 | 2.8 | 2.007E-3 | 6.4 | 7.873E-3 | 2.6 |
6.0E+9 | 4.915E-3 | 3.0 | 1.531E-3 | 7.5 | 6.446E-3 | 2.8 |
8.0E+9 | 4.259E-3 | 3.5 | 1.190E-3 | 9.9 | 5.449E-3 | 3.4 |
1.0E+10 | 4.113E-3 | 4.0 | 1.110E-3 | 12.2 | 5.222E-3 | 4.0 |
1.5E+10 | 4.067E-3 | 4.0 | 1.085E-3 | 12.2 | 5.152E-3 | 4.0 |
2.0E+10 | 4.062E-3 | 4.0 | 1.083E-3 | 12.2 | 5.146E-3 | 4.0 |
3.0E+10 | 4.058E-3 | 4.0 | 1.081E-3 | 12.2 | 5.138E-3 | 4.0 |
4.0E+10 | 4.054E-3 | 4.0 | 1.078E-3 | 12.2 | 5.132E-3 | 4.0 |
5.0E+10 | 4.050E-3 | 4.0 | 1.076E-3 | 12.2 | 5.126E-3 | 4.0 |
6.0E+10 | 4.046E-3 | 4.0 | 1.074E-3 | 12.3 | 5.119E-3 | 4.0 |
8.0E+10 | 4.037E-3 | 4.0 | 1.069E-3 | 12.3 | 5.106E-3 | 4.0 |
1.0E+11 | 4.029E-3 | 4.0 | 1.064E-3 | 12.3 | 5.094E-3 | 4.0 |
1.5E+11 | 4.009E-3 | 4.0 | 1.053E-3 | 12.3 | 5.062E-3 | 4.0 |
2.0E+11 | 3.989E-3 | 4.0 | 1.041E-3 | 12.3 | 5.030E-3 | 4.0 |
3.0E+11 | 3.950E-3 | 3.9 | 1.018E-3 | 12.3 | 4.968E-3 | 3.9 |
4.0E+11 | 3.911E-3 | 3.9 | 9.963E-4 | 12.3 | 4.907E-3 | 3.9 |
5.0E+11 | 3.872E-3 | 3.9 | 9.746E-4 | 12.3 | 4.847E-3 | 3.9 |
6.0E+11 | 3.834E-3 | 3.8 | 9.535E-4 | 12.3 | 4.787E-3 | 3.8 |
8.0E+11 | 3.759E-3 | 3.8 | 9.125E-4 | 12.3 | 4.672E-3 | 3.8 |
1.0E+12 | 3.686E-3 | 3.8 | 8.732E-4 | 12.3 | 4.560E-3 | 3.8 |
1.5E+12 | 3.512E-3 | 3.7 | 7.824E-4 | 12.9 | 4.294E-3 | 3.7 |
2.0E+12 | 3.348E-3 | 3.6 | 7.010E-4 | 13.5 | 4.049E-3 | 3.7 |
3.0E+12 | 3.049E-3 | 3.5 | 5.627E-4 | 14.7 | 3.611E-3 | 3.5 |
4.0E+12 | 2.783E-3 | 3.3 | 4.517E-4 | 15.9 | 3.235E-3 | 3.4 |
5.0E+12 | 2.547E-3 | 3.1 | 3.626E-4 | 17.1 | 2.910E-3 | 3.3 |
6.0E+12 | 2.337E-3 | 3.0 | 2.911E-4 | 18.9 | 2.628E-3 | 3.1 |
8.0E+12 | 1.981E-3 | 2.6 | 1.877E-4 | 20.8 | 2.169E-3 | 2.9 |
1.0E+13 | 1.695E-3 | 2.3 | 1.210E-4 | 23.2 | 1.816E-3 | 2.6 |
|
Copyright © 1995-2014
日本原子力研究開発機構 核データ研究グループ 〒319-1195
茨城県那珂郡東海村白方白根 2-4
|