Fission product yield




Nuclear fission splits a heavy nucleus such as uranium or plutonium into two lighter nuclei, which are called fission products. Yield refers to the fraction of a fission product produced per fission.
Yield can be broken down by:
  1. Individual isotope
  2. Chemical element spanning several isotopes of different mass number but same atomic number.
  3. Nuclei of a given mass number regardless of atomic number. Known as "chain yield" because it represents a decay chain of beta decay.
Isotope and element yields will change as the fission products undergo beta decay, while chain yields do not change after completion of neutron emission by a few neutron-rich initial fission products, with half-life measured in seconds.
A few isotopes can be produced directly by fission, but not by beta decay because the would-be precursor with atomic number one greater is stable and does not decay. Chain yields do not account for these "shadowed" isotopes; however, they have very low yields because they are far less neutron-rich than the original heavy nuclei.
Yield is usually stated as percentage per fission, so that the total yield percentages sum to 200%. Less often, it is stated as percentage of all fission products, so that the percentages sum to 100%.
Ternary fission, about 0.2% to 0.4% of fissions, also produces a third light nucleus such as helium-4 or tritium.

Mass vs. yield curve

If a graph of the mass or mole yield of fission products against the atomic number of the fragments is drawn then it has two peaks, one in the area zirconium through to palladium and one at xenon through to neodymium. This is because the fission event causes the nucleus to split in an asymmetric manner, as nuclei closer to magic numbers are more stable.
Yield vs. Z - This is a typical distribution for the fission of uranium. Note that in the calculations used to make this graph the activation of fission products was ignored and the fission was assumed to occur in a single moment rather than a length of time. In this bar chart results are shown for different cooling times.
, which is important in nuclear reprocessing: Blue elements have volatile fluorides or are already volatile; green elements do not but have volatile chlorides; red elements have neither, but the elements themselves are volatile at very high temperatures. Yields at 100,1,2,3 years after fission, not considering later neutron capture, fraction of 100% not 200%. Beta decay Kr-85→Rb, Sr-90→Zr, Ru-106→Pd, Sb-125→Te, Cs-137→Ba, Ce-144→Nd, Sm-151→Eu, Eu-155→Gd visible.
Because of the stability of nuclei with even numbers of protons and/or neutrons the curve of yield against element is not a smooth curve. It tends to alternate.
In general, the higher the energy of the state that undergoes nuclear fission, the more likely a symmetric fission is, hence as the neutron energy increases and/or the energy of the fissile atom increases, the valley between the two peaks becomes more shallow; for instance, the curve of yield against mass for Pu-239 has a more shallow valley than that observed for U-235, when the neutrons are thermal neutrons. The curves for the fission of the later actinides tend to make even more shallow valleys. In extreme cases such as 259Fm, only one peak is seen.
Yield is usually expressed relative to number of fissioning nuclei, not the number of fission product nuclei, that is, yields should sum to 200%.
The table in the next section gives yields for notable radioactive fission products, and neutron poison fission products, from thermal neutron fission of U-235, computed from .
The yields in the table sum to only 45.5522%, including 34.8401% which have half-lives greater than one year:
t½ in yearsyield
1 to 52.7252%
10 to 10012.5340%
2 to 300,0006.1251%
1.5 to 16 million13.4494%

The remainder and the unlisted 54.4478% decay with half-lives less than one year into nonradioactive nuclei.
This is before accounting for the effects of any subsequent neutron capture, e.g.:
Besides fission products, the other types of radioactive products are

Cumulative Fission Yields

Cumulative fission yields give the amounts of nuclides produced either directly in the fission or by decay of other nuclides.
ProductThermal Fission YieldFast Fission Yield14-MeV Fission Yield
0.00171 ± 0.000180.00269 ± 0.000440.00264 ± 0.00045
0.00084 ± 0.000150.00082 ± 0.000120.00081 ± 0.00012
0.0108 ± 0.00040.0108 ± 0.00040.0174 ± 0.0036
0.0108 ± 0.00040.0108 ± 0.00040.0174 ± 0.0036
0.1702 ± 0.00490.17 ± 0.00490.1667 ± 0.0088
1.304 ± 0.0121.309 ± 0.0431.64 ± 0.31
0.000285 ± 0.0000760.00044 ± 0.000160.038 ± 0.012
0.286 ± 0.0210.286 ± 0.0260.47 ± 0.1
1.303 ± 0.0121.307 ± 0.0431.65 ± 0.31
5.73 ± 0.135.22 ± 0.184.41 ± 0.18
6.502 ± 0.0726.349 ± 0.0835.07 ± 0.19
0.00000042 ± 0.000000112.90 x 10−8 ± 7.70 x 10−90.00004 ± 0.000015
6.498 ± 0.0726.345 ± 0.0835.07 ± 0.19
0.0702 ± 0.00670.0686 ± 0.00710.0548 ± 0.0072
0 ± 00 ± 00 ± 0
8.70 x 10−10 ± 3.20 x 10−100 ± 06.20 x 10−8 ± 2.50 x 10−8
0.00042 ± 0.000150.000069 ± 0.0000250.0033 ± 0.0015
6.132 ± 0.0925.8 ± 0.135.02 ± 0.13
6.132 ± 0.0925.8 ± 0.135.02 ± 0.13
3.103 ± 0.0843.248 ± 0.0423.14 ± 0.11
0.41 ± 0.0110.469 ± 0.0362.15 ± 0.59
0.41 ± 0.0110.469 ± 0.0362.15 ± 0.59
0.00106 ± 0.000110.0039 ± 0.000910.142 ± 0.023
0.000000366 ± 0.0000000980.0000004 ± 0.000000140.00193 ± 0.00068
0.000089 ± 0.0000210.000112 ± 0.0000340.027 ± 0.01
0.026 ± 0.00140.067 ± 0.0111.42 ± 0.42
4.276 ± 0.0434.639 ± 0.0653.85 ± 0.16
0.706 ± 0.0321.03 ± 0.261.59 ± 0.18
2.878 ± 0.0323.365 ± 0.0544.11 ± 0.14
6.59 ± 0.116.61 ± 0.135.42 ± 0.4
6.39 ± 0.226.01 ± 0.184.8 ± 1.4
0 ± 00 ± 00.00108 ± 0.00048
0.000038 ± 0.00000980.000152 ± 0.0000550.038 ± 0.014
0.0313 ± 0.0030.0365 ± 0.00310.047 ± 0.0049
6.6 ± 0.116.61 ± 0.135.57 ± 0.41
0.189 ± 0.0150.19 ± 0.0150.281 ± 0.049
6.61 ± 0.226.32 ± 0.186.4 ± 1.8
1.22 ± 0.121.23 ± 0.132.17 ± 0.66
0.0000121 ± 0.00000320.0000279 ± 0.00000730.0132 ± 0.0035
6.221 ± 0.0695.889 ± 0.0965.6 ± 1.3
6.314 ± 0.0955.959 ± 0.0484.474 ± 0.081
6.315 ± 0.0955.96 ± 0.0484.508 ± 0.081
5.86 ± 0.155.795 ± 0.0814.44 ± 0.2
5.474 ± 0.0555.094 ± 0.0763.154 ± 0.038
5.474 ± 0.0555.094 ± 0.0763.155 ± 0.038
6.30 x 10−9 ± 1.70 x 10−91.70 x 10−9 ± 4.80 x 10−100.0000137 ± 0.0000049
5.475 ± 0.0555.094 ± 0.0763.155 ± 0.038
2.232 ± 0.042.148 ± 0.0281.657 ± 0.045
2.232 ± 0.042.148 ± 0.0281.657 ± 0.045
5.00 x 10−8 ± 1.70 x 10−87.40 x 10−9 ± 2.50 x 10−90.0000013 ± 0.00000042
0.000000104 ± 0.0000000391.78 x 10−8 ± 6.60 x 10−90.0000048 ± 0.0000018
1.053 ± 0.0211.064 ± 0.030.557 ± 0.09
0.4204 ± 0.00710.431 ± 0.0150.388 ± 0.061
0.000000149 ± 0.0000000412.43 x 10−8 ± 6.80 x 10−90.0000058 ± 0.0000018
0.000061 ± 0.0000220.0000201 ± 0.00000770.00045 ± 0.00018
0.4204 ± 0.00710.431 ± 0.0150.388 ± 0.061
0.1477 ± 0.00710.1512 ± 0.00970.23 ± 0.015
0.4204 ± 0.00710.431 ± 0.0150.388 ± 0.061
3.24 x 10−10 ± 8.50 x 10−110 ± 03.30 x 10−8 ± 1.10 x 10−8
0.000000195 ± 0.0000000644.00 x 10−8 ± 1.10 x 10−80.0000033 ± 0.0000011
0.0308 ± 0.00130.044 ± 0.010.088 ± 0.014

ProductThermal Fission YieldFast Fission Yield14-MeV Fission Yield
0.00408 ± 0.000410.00346 ± 0.00057-
0.00135 ± 0.000190.00106 ± 0.00016-
0.0142 ± 0.00070.0142 ± 0.0007-
0.0142 ± 0.00070.0142 ± 0.0007-
0.2192 ± 0.0090.219 ± 0.009-
0.574 ± 0.0260.617 ± 0.049-
0.00175 ± 0.00060.00055 ± 0.0002-
0.136 ± 0.0140.138 ± 0.017-
0.576 ± 0.0260.617 ± 0.049-
2.013 ± 0.0542.031 ± 0.057-
4.949 ± 0.0994.682 ± 0.098-
0.0000168 ± 0.00000450.00000255 ± 0.00000069-
4.946 ± 0.0994.68 ± 0.098-
0.0535 ± 0.00660.0506 ± 0.0062-
0 ± 00 ± 0-
3.60 x 10−8 ± 1.30 x 10−84.80 x 10−9 ± 1.70 x 10−9-
0.0051 ± 0.00180.0017 ± 0.00062-
6.185 ± 0.0565.82 ± 0.13-
6.184 ± 0.0565.82 ± 0.13-
6.948 ± 0.0836.59 ± 0.16-
4.188 ± 0.0924.13 ± 0.24-
4.188 ± 0.0924.13 ± 0.24-
0.0052 ± 0.00110.0053 ± 0.0012-
0.000024 ± 0.00000630.0000153 ± 0.000005-
0.00228 ± 0.000490.00154 ± 0.00043-
0.117 ± 0.0150.138 ± 0.022-
5.095 ± 0.0944.92 ± 0.32-
1.407 ± 0.0861.31 ± 0.13-
3.724 ± 0.0784.09 ± 0.12-
6.97 ± 0.136.99 ± 0.33-
6.33 ± 0.236.24 ± 0.22-
0.00000234 ± 0.000000850.0000025 ± 0.0000012-
0.00166 ± 0.000560.00231 ± 0.00085-
0.0405 ± 0.0040.0444 ± 0.0044-
6.99 ± 0.137.03 ± 0.33-
0.216 ± 0.0160.223 ± 0.021-
7.36 ± 0.247.5 ± 0.23-
1.78 ± 0.211.97 ± 0.25-
0.00067 ± 0.000180.00115 ± 0.0003-
6.588 ± 0.086.35 ± 0.12-
5.322 ± 0.0595.303 ± 0.074-
5.333 ± 0.0595.324 ± 0.075-
5.205 ± 0.0735.01 ± 0.16-
3.755 ± 0.033.504 ± 0.053-
3.756 ± 0.033.505 ± 0.053-
0.00000145 ± 0.00000040.00000251 ± 0.00000072-
3.756 ± 0.033.505 ± 0.053-
2.044 ± 0.0391.929 ± 0.046-
2.044 ± 0.0391.929 ± 0.046-
0.0000056 ± 0.00000190.000012 ± 0.000004-
0.0000118 ± 0.00000440.000029 ± 0.000011-
1.263 ± 0.0321.275 ± 0.056-
0.776 ± 0.0180.796 ± 0.037-
0.0000168 ± 0.00000460.000039 ± 0.000011-
0.00227 ± 0.000780.0051 ± 0.0019-
0.776 ± 0.0180.797 ± 0.037-
0.38 ± 0.030.4 ± 0.18-
0.776 ± 0.0180.797 ± 0.037-
0.000000195 ± 0.000000050.00000048 ± 0.00000014-
0.000049 ± 0.0000120.000127 ± 0.000043-
0.174 ± 0.030.171 ± 0.054-

JEFF-3.1Joint Evaluated Fission and Fusion File, Incident-neutron data,
http://www-nds.iaea.org/exfor/endf00.htm, 2 October 2006;
see also A. Koning, R. Forrest, M. Kellett, R. Mills, H. Henriksson,
Y. Rugama, The JEFF-3.1 Nuclear Data Library, JEFF Report 21,
OECD/NEA, Paris, France, 2006,.

not U-235 because left hump is shifted right, not considering later neutron capture, fraction of 100% not 200%. Beta decay Kr-85→Rb, Sr-90→Zr, Ru-106→Pd, Sb-125→Te, Cs-137→Ba, Ce-144→Nd, Sm-151→Eu, Eu-155→Gd visible.

Ordered by mass number

Half lives, decay modes, and branching fractions

NuclideHalf-lifeDecay modeBranching fractionSourceNotes
2.9 ± 0.06 mβ1.0ENSDF
10.752 ± 0.023 yβ1.0BIPM-5-
4.48 ± 0.008 hIT0.214 ± 0.005ENSDF-
4.48 ± 0.008 hβ0.786 ± 0.005ENSDF-
28.8 ± 0.07 yβ1.0LNHB-
64.032 ± 0.006 dβ1.0LNHB-
x 106 dβ1.0IAEA-CRP-XG-
3.61 ± 0.03 dβ0.025 ± 0.001LNHB
3.61 ± 0.03 dIT0.975 ± 0.001LNHB
34.985 ± 0.012 dβ1.0IAEA-CRP-XG-
x 105 yβ1.0ENSDF-
39.247 ± 0.013 dβ1.0IAEA-CRP-XG-
1.018 ± 0.005 yβ1.0IAEA-CRP-XG-
30.1 ± 0.3 sβ1.0IAEA-CRP-XG-
55 ± 5 yβ0.224 ± 0.02ENSDF-
55 ± 5 yIT0.776 ± 0.02ENSDF-
2.7238 ± 0.0002 dEC0.0241 ± 0.0012ENSDF-
2.7238 ± 0.0002 dβ0.9759 ± 0.0012ENSDF-
60.2 ± 0.03 dβ1.0ENSDF-
2.7584 ± 0.0006 yβ1.0IAEA-CRP-XG-
x 109 dβ1.0IAEA-CRP-XG-
8.0233 ± 0.0019 dβ1.0BIPM-5-
20.87 ± 0.08 hβ1.0LNHB
6.57 ± 0.02 hβ1.0ENSDF-
11.930 ± 0.016 dIT1.0BIPM-5-
5.243 ± 0.001 dβ1.0ENSDF-
2.19 ± 0.01 dIT1.0ENSDF-
9.14 ± 0.02 hβ1.0ENSDF-
15.29 ± 0.05 mβ0.003 ± 0.003ENSDF
15.29 ± 0.05 mIT0.997 ± 0.003ENSDF
2.063 ± 0.003 yEC0.000003 ± 0.000001IAEA-CRP-XG
2.063 ± 0.003 yβ0.999997 ± 0.000001IAEA-CRP-XG
30.05 ± 0.08 yβ1.0IAEA-CRP-XG-
12.753 ± 0.004 dβ1.0BIPM-5-
1.67850 ± 0.00017 dβ1.0BIPM-5-
32.508 ± 0.010 dβ1.0LNHB-
285.1 ± 0.6 dβ1.0IAEA-CRP-XG-
17.28 ± 0.05 mβ1.0ENSDF-
10.98 ± 0.01 dβ1.0ENSDF-
2.6234 ± 0.0002 yβ1.0ENSDF-
41.29 ± 0.11 dIT0.042 ± 0.007ENSDF-
41.29 ± 0.11 dβ0.958 ± 0.007ENSDF-
5.368 ± 0.002 dβ1.0ENSDF-
2.2117 ± 0.0021 dβ1.0ENSDF-
1.1833 ± 0.0017 dβ1.0ENSDF-
90 ± 6 yβ1.0ENSDF-
1.938 ± 0.010 dβ1.0IAEA-CRP-XG-
x 103 dβ0.279 ± 0.003IAEA-CRP-XG
x 103 dEC0.721 ± 0.003IAEA-CRP-XG
x 103 dEC0.00018 ± 0.00013IAEA-CRP-XG
x 103 dβ0.99982 ± 0.00013IAEA-CRP-XG
4.753 ± 0.016 yβ1.0IAEA-CRP-XG-

BIPM-5M.-M. Bé, V. Chisté, C. Dulieu, E. Browne, V. Chechev, N. Kuzmenko, R. Helmer, A. Nichols,
E. Schönfeld, R. Dersch, Monographie BIPM-5, Table of Radionuclides, Vol. 2 - A = 151 to 242, 2004.
LNHBLaboratoire National Henri Becquerel, Recommended Data,
http://www.nucleide.org/DDEP_WG/DDEPdata.htm, 16 January 2006.
IAEA-CRP-XGM.-M. Bé, V.P. Chechev, R. Dersch, O.A.M. Helene, R.G. Helmer, M. Herman, S. Hlavác,
A. Marcinkowski, G.L. Molnár, A.L. Nichols, E. Schönfeld, V.R. Vanin, M.J. Woods, IAEA CRP "Update of X-ray and Gamma-ray Decay Data Standards for Detector Calibration and Other Applications", IAEA Scientific and Technical Information report STI/PUB/1287, May 2007, International Atomic Energy Agency, Vienna, Austria,.
ENSDFEvaluated Nuclear Structure Data File, http://www-nds.iaea.org/ensdf/, 26 January 2006.

β- decay branches of 0.9982 ± 0.0002 to Kr-85m and 0.0018 ± 0.0002 to Kr-85.
ENSDF branching fractions: 0.944 ± 0.007 for IT and 0.056 ± 0.007 for β-.
β- decay branch of 0.0288 ± 0.0002 to Xe-133m.
Branching fractions were averaged from ENSDF database.
Branching fractions were adopted from ENSDF database.
Branching fractions were adopted from LNHB data.

Ordered by thermal neutron neutron absorption cross section