View source for Fission product yield

{{Short description|Fractions of products of nuclear fission}}
<div style="float:right; margin:0.25em;">{{Long-lived fission products}}</div>
<div style="float:right; margin:0.25em;">{{Medium-lived fission products}}</div>

[[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:
# Individual [[isotope]]
# [[Chemical element]] spanning several isotopes of different [[mass number]] but same [[atomic number]].
# 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 ([[delayed neutron]]s), 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 less is stable and does not decay (atomic number grows by 1 during beta decay). Chain yields do not account for these "shadowed" isotopes; however, they have very low yields (less than a millionth as much as common fission products) 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%.{{cn|date=June 2025}} Less often, it is stated as percentage of all fission product.{{cn|date=June 2025}}

== Definitions ==
There are several types of yields. For the most common fission reactions, the decay of the fission products preserve mass number. Thus the products form decay chains of constant mass. That makes the ''independent yield'' especially useful.<ref name=Mills-PhD>Mills, R. W. (1995). Fission product yield evaluation (Doctoral dissertation, University of Birmingham).</ref>{{rp|9}}

The ''independent yield'' is a product of three factors, Y(A) the ''sum yield'' or ''mass yield'', <math>f(A,Z)</math> the ''fractional independent yield'', and R(A,Z,I) the isomeric yield ratio:<ref name=Mills-PhD/>
<math display="block">\textrm{y}(A,Z,I) = \textrm{Y}(A)\cdot f(A,Z) \cdot R(A,Z,I)</math>
Here possible product of fission can be represented by a triplet (A,Z,I), where A is the [[mass number]], Z is the [[atomic number]], and I is an integer for [[Nuclear isomer|isomeric excited state]], numbered from 0 for the ground state.
For each decay chain (mass number A) the fractional independent yields and isomeric yield formulas sum to one:
<math display="block">\Sigma_Z f(A,Z) = \Sigma_I R(A,Z,I) = 1</math> 
and the independent yields sum to the sum yield for each chain:
<math display="block">\textrm{Y}(A) = \Sigma_{Z,I} \textrm{y}(A,Z,I).</math>
The independent yield excludes delayed neutron emission. The ''cumulative yield,'', c(A,Z,I), of a nuclide (A,Z,I) is the total number of atoms produced by one fission over all time. The ''chain yield'', Ch(A), is the sum of all the cumulative yields for one mass chain for one fission. The independent, cumulative, and chain yields are given as percent per fission, that is as the yield of products per 100 fission reaction.<ref name=Mills-PhD/>

== Mass vs. yield curve ==

[[Image:ThermalFissionYield.svg|thumb|450px|Fission product yields by mass for thermal neutron fission of U-235, Pu-239, a combination of the two typical of current nuclear power reactors, and U-233 used in the [[thorium fuel cycle]]]]

If a graph of the [[mass]] or [[mole (unit)|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,<ref>{{Cite web |url=http://www.science.uwaterloo.ca/~cchieh/cact/nuctek/fissionyield.html |title=fissionyield |access-date=2007-06-10 |archive-url=https://web.archive.org/web/20070528055359/http://www.science.uwaterloo.ca/~cchieh/cact/nuctek/fissionyield.html |archive-date=2007-05-28 |url-status=dead }}</ref> as nuclei closer to [[Magic number (physics)|magic numbers]] are more stable.<ref name="NatureMagicNumbers">{{cite journal|title=Nuclear fission modes and fragment mass asymmetries in a five-dimensional deformation space|journal=Nature|date=15 February 2001|volume=409|issue=6822|pages=785–790|doi=10.1038/35057204|pmid=11236985 | last1 = Möller | first1 = P | last2 = Madland | first2 = DG | last3 = Sierk | first3 = AJ | last4 = Iwamoto | first4 = A|bibcode=2001Natur.409..785M|s2cid=9754793|url=https://zenodo.org/record/1233095}}
</ref>

'''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 (time after fission).
[[File:Fission yield volatile 2.png|thumb|450px|Yield vs Z. Colors indicate [[fluoride volatility]], 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 10<sup>0,1,2,3</sup> years after [[Nuclear fission|fission]], not considering later [[neutron capture]], fraction of 100% not 200%. [[Beta decay]] [[Kr-85]]→[[rubidium|Rb]], [[Sr-90]]→[[zirconium|Zr]], [[Ru-106]]→[[palladium|Pd]], [[Sb-125]]→[[tellurium|Te]], [[Cs-137]]→[[barium|Ba]], [[Ce-144]]→[[neodymium|Nd]], [[Sm-151]]→[[europium|Eu]], [[Eu-155]]→[[gadolinium|Gd]] visible.]]

Because of the stability of nuclei with even numbers of [[proton]]s and/or [[neutron]]s 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 [[Uranium-235|U-235]], when the neutrons are [[thermal neutron]]s. The curves for the fission of the later [[actinides]] tend to make even more shallow valleys. In extreme cases such as <sup>259</sup>Fm, 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 ("Ordered by yield") gives yields for notable [[radioactive]] (with [[half-life|half-lives]] greater than one year, plus [[iodine-131]]) [[fission product]]s, and (the few most absorptive) [[neutron poison]] fission products, from [[thermal neutron]] fission of [[Uranium-235|U-235]] (typical of [[nuclear power]] reactors), computed from [http://books.elsevier.com/companions/075067136X/pdfs/Yield.bas?mscssid=HAX80JCKT7RB8LS6F675GU2LM83N1CL6]{{Dead link|date=December 2019 |bot=InternetArchiveBot |fix-attempted=yes }}.

The yields in the table sum to only 45.5522%, including 34.8401% which have half-lives greater than one year:

{| class="wikitable" style="text-align:right;"
! ''t''<sub>½</sub> in years !! Yield
|-
| 1 to 5            ||  2.7252%
|-
| 10 to 100         || 12.5340%
|-
| 2 to 300,000      ||  6.1251%
|-
| 1.5 to 16 million || 13.4494%
|}

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.:
* [[Xenon-135|<sup>135</sup>Xe]] capturing a neutron and becoming nearly stable <sup>136</sup>Xe, rather than decaying to <sup>135</sup>Cs which is radioactive with a half-life of 2.3 million years
* Nonradioactive <sup>133</sup>Cs capturing a neutron and becoming <sup>134</sup>Cs, which is radioactive with a half-life of 2 years
* Many of the fission products with mass 147 or greater such as [[promethium-147|<sup>147</sup>Pm]], [[Samarium-149|<sup>149</sup>Sm]], [[samarium-151|<sup>151</sup>Sm]], and [[europium-155|<sup>155</sup>Eu]] have significant cross sections for neutron capture, so that one heavy fission product atom can undergo multiple successive neutron captures.

Besides fission products, the other types of radioactive products are

* [[plutonium]] containing [[Pu-238|<sup>238</sup>Pu]], [[Pu-239|<sup>239</sup>Pu]], [[Pu-240|<sup>240</sup>Pu]], [[Pu-241|<sup>241</sup>Pu]], and [[Pu-242|<sup>242</sup>Pu]],
* [[minor actinides]] including [[Np-237|<sup>237</sup>Np]], [[Am-241|<sup>241</sup>Am]], [[Americium|<sup>243</sup>Am]], [[curium]] isotopes, and perhaps [[californium]]
* [[reprocessed uranium]] containing [[Uranium-236|<sup>236</sup>U]] and other isotopes
* [[tritium]]
* [[activation products]] of neutron capture by the reactor or bomb structure or the environment

==Fission products from U-235==
{| class="wikitable sortable"
! Yield !! Element !! Isotope<!-- Sorted by mass; could be by symbol, or name. --> !! Halflife !! Comment
|-
| 6.7896% || [[Caesium]] || {{hs|133 !}} [[caesium-133|<sup>133</sup>Cs]] [[neutron capture|→]] [[caesium-134|<sup>134</sup>Cs]] || {{ntsh|2}} 2.065 y || [[Neutron capture]] (29 barns) slowly converts stable <sup>133</sup>Cs to <sup>134</sup>Cs, which itself is low-yield because [[beta decay]] stops at <sup>134</sup>Xe; can be further converted (140 barns) to [[Cs-135|<sup>135</sup>Cs]].
|-
| 6.3333% || [[Iodine]], [[xenon]] || {{hs|135 !}} [[iodine-135|<sup>135</sup>I]] [[beta decay|→]] [[xenon-135|<sup>135</sup>Xe]] || {{ntsh|0.0006}} 6.57 h || Most important [[neutron poison]]; [[neutron capture]] converts 10–50% of <sup>135</sup>Xe to <sup>136</sup>Xe; remainder decays (9.14h) to [[Cs-135|<sup>135</sup>Cs]] (2.3 My).
|-
| 6.2956% || [[Zirconium]] || {{hs|93 !}} [[Zr-93|<sup>93</sup>Zr]] || {{ntsh|1530000}} 1.53 My || [[Long-lived fission product]] also produced by [[neutron activation]] in [[zircalloy]] cladding.
|-
| 6.1%    || [[Molybdenum]] || {{hs|98.9077 !}} [[Mo-99|<sup>99</sup>Mo]] || {{ntsh|0.003}} 65.94 h || Its daughter nuclide [[Tc-99m|<sup>99m</sup>Tc]] is important in medical diagnosing.
|-
| 6.0899% || [[Caesium]] || {{hs|137 !}} [[Cs-137|<sup>137</sup>Cs]] || {{ntsh|30}} 30.17 y || Source of most of the [[decay heat]] from years to decades after irradiation, together with {{chem|90|Sr}}.
|-
| 6.0507% || [[Technetium]] || {{hs|98.9063 !}} [[Tc-99|<sup>99</sup>Tc]] || {{ntsh|211000}} 211 ky || Candidate for disposal by [[nuclear transmutation]].
|-
| 5.7518% || [[Strontium]] || {{hs|90 !}} [[strontium-90|<sup>90</sup>Sr]] || {{ntsh|29}} 28.9 y || Source of much of the decay heat together with {{chem|137|Cs}} on the timespan of  years to decades after irradiation. Formerly used in [[radioisotope thermoelectric generator]]s.
|-
| 2.8336% || [[Iodine]] || {{hs|131 !}} [[iodine-131|<sup>131</sup>I]] || {{ntsh|0.008}} 8.02 d || Reason for the use of [[potassium iodide]] tablets after nuclear accidents or nuclear bomb explosions.
|-
| 2.2713% || [[Promethium]] || {{hs|147 !}} [[promethium-147|<sup>147</sup>Pm]] || {{ntsh|2.6}} 2.62 y || beta decays to very long lived Samarium-147 (half life>[[age of the universe]]); has seen some use in [[radioisotope thermoelectric generator]]s
|-
| 1.0888% || [[Samarium]] || {{hs|149 !}} [[samarium-149|<sup>149</sup>Sm]] || {{ntsh|100000000}} Observationally stable || 2nd most significant [[neutron poison]].
|-
| 0.9%<ref>Purkayastha, B. C., and G. R. Martin. "The yields of 129I in natural and in neutron-induced fission of uranium." Canadian Journal of Chemistry 34.3 (1956): 293-300.</ref> || [[Iodine]] || {{hs|129 !}} [[iodine-129|<sup>129</sup>I]] || {{ntsh|15700000}} 15.7 My || [[Long-lived fission product]]. Candidate for disposal by [[nuclear transmutation]].
|-
| 0.4203% || [[Samarium]] || {{hs|151 !}} [[samarium-151|<sup>151</sup>Sm]] || {{ntsh|90}} 90 y || [[Neutron poison]]; most will be converted to stable <sup>152</sup>Sm.
|-
| 0.3912% || [[Ruthenium]] || {{hs|106 !}} [[ruthenium-106|<sup>106</sup>Ru]] || {{ntsh|1}} 373.6 d|| [[ruthenium tetroxide]] is volatile and chemically aggressive; [[daughter nuclide]] {{chem|106|Rh}} decays quickly to stable {{chem|106|Pd}}
|-
| 0.2717% || [[Krypton]] || {{hs|85 !}} [[krypton-85|<sup>85</sup>Kr]] || {{ntsh|11}} 10.78 y || [[noble gas]]; has some uses in industry to detect fine cracks in materials via [[autoradiography]]
|-
| 0.1629% || [[Palladium]] || {{hs|107 !}} [[palladium-107|<sup>107</sup>Pd]] || {{ntsh|6500000}} 6.5 My || [[Long-lived fission product]]; hampers extraction of stable isotopes of [[platinum group]] metals for use due to chemical similarity.
|-
| 0.0508% || [[Selenium]] || {{hs|79 !}} [[selenium-79|<sup>79</sup>Se]] || {{ntsh|327000}} 327 ky
|-
| 0.0330% || [[Europium]], [[gadolinium]] || {{hs|155 !}} [[europium-155|<sup>155</sup>Eu]] [[beta decay|→]] [[gadolinium-155|<sup>155</sup>Gd]] || {{ntsh|5}} 4.76 y || Both [[neutron poison]]s, most will be destroyed while fuel still in use.
|-
| 0.0297% || [[Antimony]] || {{hs|125 !}} [[antimony-125|<sup>125</sup>Sb]] || {{ntsh|2.8}} 2.76 y
|-
| 0.0236% || [[Tin]] || {{hs|126 !}} [[tin-126|<sup>126</sup>Sn]] || {{ntsh|230000}} 230 ky
|-
| 0.0065% || [[Gadolinium]] || {{hs|157 !}} [[gadolinium-157|<sup>157</sup>Gd]] || {{ntsh|100000000}} stable || [[Neutron poison]].
|-
| 0.0003% || [[Cadmium]] || {{hs|133 !}} [[cadmium-113m|<sup>113m</sup>Cd]] || {{ntsh|14}} 14.1 y || [[Neutron poison]], most will be destroyed while fuel still in use.
|}

[[Image:fission yield.png|none|thumb|450px|Yields at 10<sup>0,1,2,3</sup> years after [[nuclear fission|fission]], probably of [[Pu-239]] not [[Uranium-235|U-235]] because left hump is shifted right, not considering later [[neutron capture]], fraction of 100% not 200%. [[Beta decay]] [[Kr-85]]→[[rubidium|Rb]], [[Sr-90]]→[[zirconium|Zr]], [[Ru-106]]→[[palladium|Pd]], [[Sb-125]]→[[tellurium|Te]], [[Cs-137]]→[[barium|Ba]], [[Ce-144]]→[[neodymium|Nd]], [[Sm-151]]→[[europium|Eu]], [[Eu-155]]→[[gadolinium|Gd]] visible.]]

==Cumulative fission yields==
Cumulative fission yields give the amounts of nuclides produced either directly in the fission or by decay of other nuclides.
{| class="wikitable" style="text-align:center;"
|-
|+ Cumulative fission yields per fission for U-235 (%)<ref name="IAEA-C3">{{cite web|title=Cumulative Fission Yields |url=https://www-nds.iaea.org/sgnucdat/c3.htm|website=www-nds.iaea.org|publisher=IAEA|access-date=11 November 2016}}</ref>
|-
! Product
! Thermal fission yield
! Fast fission yield
! 14-MeV fission yield
|-
| {{nuclide|H|1}} || 0.00171 ± 0.00018 || 0.00269 ± 0.00044 || 0.00264 ± 0.00045
|-
| {{nuclide|H|2}} || 0.00084 ± 0.00015 || 0.00082 ± 0.00012 || 0.00081 ± 0.00012
|-
| {{nuclide|H|3}} || 0.0108 ± 0.0004 || 0.0108 ± 0.0004 || 0.0174 ± 0.0036
|-
| {{nuclide|He|3}} || 0.0108 ± 0.0004 || 0.0108 ± 0.0004 || 0.0174 ± 0.0036
|-
| {{nuclide|He|4}} || 0.1702 ± 0.0049 || 0.17 ± 0.0049 || 0.1667 ± 0.0088
|-
| {{nuclide|Br|85}} || 1.304 ± 0.012 || 1.309 ± 0.043 || 1.64 ± 0.31
|-
| {{nuclide|Kr|82}} || 0.000285 ± 0.000076 || 0.00044 ± 0.00016 || 0.038 ± 0.012
|-
| {{nuclide|Kr|85}} || 0.286 ± 0.021 || 0.286 ± 0.026 || 0.47 ± 0.1
|-
| {{nuclide|Kr|85m}} || 1.303 ± 0.012 || 1.307 ± 0.043 || 1.65 ± 0.31
|-
| {{nuclide|Sr|90}} || 5.73 ± 0.13 || 5.22 ± 0.18 || 4.41 ± 0.18
|-
| {{nuclide|Zr|95}} || 6.502 ± 0.072 || 6.349 ± 0.083 || 5.07 ± 0.19
|-
| {{nuclide|Nb|94}} || 0.00000042 ± 0.00000011 || 2.90±0.770 × 10<sup>−8</sup> || 0.00004 ± 0.000015
|-
| {{nuclide|Nb|95}} || 6.498 ± 0.072 || 6.345 ± 0.083 || 5.07 ± 0.19
|-
| {{nuclide|Nb|95m}} || 0.0702 ± 0.0067 || 0.0686 ± 0.0071 || 0.0548 ± 0.0072
|-
| {{nuclide|Mo|92}} || 0 ± 0 || 0 ± 0 || 0 ± 0
|-
| {{nuclide|Mo|94}} || 8.70 × 10<sup>−10</sup> ± 3.20 × 10<sup>−10</sup> || 0 ± 0 || 6.20 × 10<sup>−8</sup> ± 2.50 × 10<sup>−8</sup>
|-
| {{nuclide|Mo|96}} || 0.00042 ± 0.00015 || 0.000069 ± 0.000025 || 0.0033 ± 0.0015
|-
| {{nuclide|Mo|99}} || 6.132 ± 0.092 || 5.8 ± 0.13 || 5.02 ± 0.13
|-
| {{nuclide|Tc|99}} || 6.132 ± 0.092 || 5.8 ± 0.13 || 5.02 ± 0.13
|-
| {{nuclide|Ru|103}} || 3.103 ± 0.084 || 3.248 ± 0.042 || 3.14 ± 0.11
|-
| {{nuclide|Ru|106}} || 0.41 ± 0.011 || 0.469 ± 0.036 || 2.15 ± 0.59
|-
| {{nuclide|Rh|106}} || 0.41 ± 0.011 || 0.469 ± 0.036 || 2.15 ± 0.59
|-
| {{nuclide|Sn|121m}} || 0.00106 ± 0.00011 || 0.0039 ± 0.00091 || 0.142 ± 0.023
|-
| {{nuclide|Sb|122}} || 0.000000366 ± 0.000000098 || 0.0000004 ± 0.00000014 || 0.00193 ± 0.00068
|-
| {{nuclide|Sb|124}} || 0.000089 ± 0.000021 || 0.000112 ± 0.000034 || 0.027 ± 0.01
|-
| {{nuclide|Sb|125}} || 0.026 ± 0.0014 || 0.067 ± 0.011 || 1.42 ± 0.42
|-
| {{nuclide|Te|132}} || 4.276 ± 0.043 || 4.639 ± 0.065 || 3.85 ± 0.16
|-
| {{nuclide|I|129}} || 0.706 ± 0.032 || 1.03 ± 0.26 || 1.59 ± 0.18
|-
| {{nuclide|I|131}} || 2.878 ± 0.032 || 3.365 ± 0.054 || 4.11 ± 0.14
|-
| {{nuclide|I|133}} || 6.59 ± 0.11 || 6.61 ± 0.13 || 5.42 ± 0.4
|-
| {{nuclide|I|135}} || 6.39 ± 0.22 || 6.01 ± 0.18 || 4.8 ± 1.4
|-
| {{nuclide|Xe|128}} || 0 ± 0 || 0 ± 0 || 0.00108 ± 0.00048
|-
| {{nuclide|Xe|130}} || 0.000038 ± 0.0000098 || 0.000152 ± 0.000055 || 0.038 ± 0.014
|-
| {{nuclide|Xe|131m}} || 0.0313 ± 0.003 || 0.0365 ± 0.0031 || 0.047 ± 0.0049
|-
| {{nuclide|Xe|133}} || 6.6 ± 0.11 || 6.61 ± 0.13 || 5.57 ± 0.41
|-
| {{nuclide|Xe|133m}} || 0.189 ± 0.015 || 0.19 ± 0.015 || 0.281 ± 0.049
|-
| {{nuclide|Xe|135}} || 6.61 ± 0.22 || 6.32 ± 0.18 || 6.4 ± 1.8
|-
| {{nuclide|Xe|135m}} || 1.22 ± 0.12 || 1.23 ± 0.13 || 2.17 ± 0.66
|-
| {{nuclide|Cs|134}} || 0.0000121 ± 0.0000032 || 0.0000279 ± 0.0000073 || 0.0132 ± 0.0035
|-
| {{nuclide|Cs|137}} || 6.221 ± 0.069 || 5.889 ± 0.096 || 5.6 ± 1.3
|-
| {{nuclide|Ba|140}} || 6.314 ± 0.095 || 5.959 ± 0.048 || 4.474 ± 0.081
|-
| {{nuclide|La|140}} || 6.315 ± 0.095 || 5.96 ± 0.048 || 4.508 ± 0.081
|-
| {{nuclide|Ce|141}} || 5.86 ± 0.15 || 5.795 ± 0.081 || 4.44 ± 0.2
|-
| {{nuclide|Ce|144}} || 5.474 ± 0.055 || 5.094 ± 0.076 || 3.154 ± 0.038
|-
| {{nuclide|Pr|144}} || 5.474 ± 0.055 || 5.094 ± 0.076 || 3.155 ± 0.038
|-
| {{nuclide|Nd|142}} || 6.30 × 10<sup>−9</sup> ± 1.70 × 10<sup>−9</sup> || 1.70 × 10<sup>−9</sup> ± 4.80 × 10<sup>−10</sup> || 0.0000137 ± 0.0000049
|-
| {{nuclide|Nd|144}} || 5.475 ± 0.055 || 5.094 ± 0.076 || 3.155 ± 0.038
|-
| {{nuclide|Nd|147}} || 2.232 ± 0.04 || 2.148 ± 0.028 || 1.657 ± 0.045
|-
| {{nuclide|Pm|147}} || 2.232 ± 0.04 || 2.148 ± 0.028 || 1.657 ± 0.045
|-
| {{nuclide|Pm|148}} || 5.00 × 10<sup>−8</sup> ± 1.70 × 10<sup>−8</sup> || 7.40 × 10<sup>−9</sup> ± 2.50 × 10<sup>−9</sup> || 0.0000013 ± 0.00000042
|-
| {{nuclide|Pm|148m}} || 0.000000104 ± 0.000000039 || 1.78 × 10<sup>−8</sup> ± 6.60 × 10<sup>−9</sup> || 0.0000048 ± 0.0000018
|-
| {{nuclide|Pm|149}} || 1.053 ± 0.021 || 1.064 ± 0.03 || 0.557 ± 0.09
|-
| {{nuclide|Pm|151}} || 0.4204 ± 0.0071 || 0.431 ± 0.015 || 0.388 ± 0.061
|-
| {{nuclide|Sm|148}} || 0.000000149 ± 0.000000041 || 2.43 × 10<sup>−8</sup> ± 6.80 × 10<sup>−9</sup> || 0.0000058 ± 0.0000018
|-
| {{nuclide|Sm|150}} || 0.000061 ± 0.000022 || 0.0000201 ± 0.0000077 || 0.00045 ± 0.00018
|-
| {{nuclide|Sm|151}} || 0.4204 ± 0.0071 || 0.431 ± 0.015 || 0.388 ± 0.061
|-
| {{nuclide|Sm|153}} || 0.1477 ± 0.0071 || 0.1512 ± 0.0097 || 0.23 ± 0.015
|-
| {{nuclide|Eu|151}} || 0.4204 ± 0.0071 || 0.431 ± 0.015 || 0.388 ± 0.061
|-
| {{nuclide|Eu|152}} || 3.24 × 10<sup>−10</sup> ± 8.50 × 10<sup>−11</sup> || 0 ± 0 || 3.30 × 10<sup>−8</sup> ± 1.10 × 10<sup>−8</sup>
|-
| {{nuclide|Eu|154}} || 0.000000195 ± 0.000000064 || 4.00 × 10<sup>−8</sup> ± 1.10 × 10<sup>−8</sup> || 0.0000033 ± 0.0000011
|-
| {{nuclide|Eu|155}} || 0.0308 ± 0.0013 || 0.044 ± 0.01 || 0.088 ± 0.014
|}

{| class="wikitable" style="text-align:center;"
|-
|+ Cumulative fission yield per fission for Pu-239 (%)<ref name="IAEA-C3"/>
|-
! Product
! Thermal fission yield
! Fast fission yield
! 14-MeV fission yield
|-
| {{nuclide|H|1}} || 0.00408 ± 0.00041 || 0.00346 ± 0.00057 || -
|-
| {{nuclide|H|2}} || 0.00135 ± 0.00019 || 0.00106 ± 0.00016 || -
|-
| {{nuclide|H|3}} || 0.0142 ± 0.0007 || 0.0142 ± 0.0007 || -
|-
| {{nuclide|He|3}} || 0.0142 ± 0.0007 || 0.0142 ± 0.0007 || -
|-
| {{nuclide|He|4}} || 0.2192 ± 0.009 || 0.219 ± 0.009 || -
|-
| {{nuclide|Br|85}} || 0.574 ± 0.026 || 0.617 ± 0.049 || -
|-
| {{nuclide|Kr|82}} || 0.00175 ± 0.0006 || 0.00055 ± 0.0002 || -
|-
| {{nuclide|Kr|85}} || 0.136 ± 0.014 || 0.138 ± 0.017 || -
|-
| {{nuclide|Kr|85m}} || 0.576 ± 0.026 || 0.617 ± 0.049 || -
|-
| {{nuclide|Sr|90}} || 2.013 ± 0.054 || 2.031 ± 0.057 || -
|-
| {{nuclide|Zr|95}} || 4.949 ± 0.099 || 4.682 ± 0.098 || -
|-
| {{nuclide|Nb|94}} || 0.0000168 ± 0.0000045 || 0.00000255 ± 0.00000069 || -
|-
| {{nuclide|Nb|95}} || 4.946 ± 0.099 || 4.68 ± 0.098 || -
|-
| {{nuclide|Nb|95m}} || 0.0535 ± 0.0066 || 0.0506 ± 0.0062 || -
|-
| {{nuclide|Mo|92}} || 0 ± 0 || 0 ± 0 || -
|-
| {{nuclide|Mo|94}} || 3.60 × 10<sup>−8</sup> ± 1.30 × 10<sup>−8</sup> || 4.80 × 10<sup>−9</sup> ± 1.70 × 10<sup>−9</sup> || -
|-
| {{nuclide|Mo|96}} || 0.0051 ± 0.0018 || 0.0017 ± 0.00062 || -
|-
| {{nuclide|Mo|99}} || 6.185 ± 0.056 || 5.82 ± 0.13 || -
|-
| {{nuclide|Tc|99}} || 6.184 ± 0.056 || 5.82 ± 0.13 || -
|-
| {{nuclide|Ru|103}} || 6.948 ± 0.083 || 6.59 ± 0.16 || -
|-
| {{nuclide|Ru|106}} || 4.188 ± 0.092 || 4.13 ± 0.24 || -
|-
| {{nuclide|Rh|106}} || 4.188 ± 0.092 || 4.13 ± 0.24 || -
|-
| {{nuclide|Sn|121m}} || 0.0052 ± 0.0011 || 0.0053 ± 0.0012 || -
|-
| {{nuclide|Sb|122}} || 0.000024 ± 0.0000063 || 0.0000153 ± 0.000005 || -
|-
| {{nuclide|Sb|124}} || 0.00228 ± 0.00049 || 0.00154 ± 0.00043 || -
|-
| {{nuclide|Sb|125}} || 0.117 ± 0.015 || 0.138 ± 0.022 || -
|-
| {{nuclide|Te|132}} || 5.095 ± 0.094 || 4.92 ± 0.32 || -
|-
| {{nuclide|I|129}} || 1.407 ± 0.086 || 1.31 ± 0.13 || -
|-
| {{nuclide|I|131}} || 3.724 ± 0.078 || 4.09 ± 0.12 || -
|-
| {{nuclide|I|133}} || 6.97 ± 0.13 || 6.99 ± 0.33 || -
|-
| {{nuclide|I|135}} || 6.33 ± 0.23 || 6.24 ± 0.22 || -
|-
| {{nuclide|Xe|128}} || 0.00000234 ± 0.00000085 || 0.0000025 ± 0.0000012 || -
|-
| {{nuclide|Xe|130}} || 0.00166 ± 0.00056 || 0.00231 ± 0.00085 || -
|-
| {{nuclide|Xe|131m}} || 0.0405 ± 0.004 || 0.0444 ± 0.0044 || -
|-
| {{nuclide|Xe|133}} || 6.99 ± 0.13 || 7.03 ± 0.33 || -
|-
| {{nuclide|Xe|133m}} || 0.216 ± 0.016 || 0.223 ± 0.021 || -
|-
| {{nuclide|Xe|135}} || 7.36 ± 0.24 || 7.5 ± 0.23 || -
|-
| {{nuclide|Xe|135m}} || 1.78 ± 0.21 || 1.97 ± 0.25 || -
|-
| {{nuclide|Cs|134}} || 0.00067 ± 0.00018 || 0.00115 ± 0.0003 || -
|-
| {{nuclide|Cs|137}} || 6.588 ± 0.08 || 6.35 ± 0.12 || -
|-
| {{nuclide|Ba|140}} || 5.322 ± 0.059 || 5.303 ± 0.074 || -
|-
| {{nuclide|La|140}} || 5.333 ± 0.059 || 5.324 ± 0.075 || -
|-
| {{nuclide|Ce|141}} || 5.205 ± 0.073 || 5.01 ± 0.16 || -
|-
| {{nuclide|Ce|144}} || 3.755 ± 0.03 || 3.504 ± 0.053 || -
|-
| {{nuclide|Pr|144}} || 3.756 ± 0.03 || 3.505 ± 0.053 || -
|-
| {{nuclide|Nd|142}} || 0.00000145 ± 0.0000004 || 0.00000251 ± 0.00000072 || -
|-
| {{nuclide|Nd|144}} || 3.756 ± 0.03 || 3.505 ± 0.053 || -
|-
| {{nuclide|Nd|147}} || 2.044 ± 0.039 || 1.929 ± 0.046 || -
|-
| {{nuclide|Pm|147}} || 2.044 ± 0.039 || 1.929 ± 0.046 || -
|-
| {{nuclide|Pm|148}} || 0.0000056 ± 0.0000019 || 0.000012 ± 0.000004 || -
|-
| {{nuclide|Pm|148m}} || 0.0000118 ± 0.0000044 || 0.000029 ± 0.000011 || -
|-
| {{nuclide|Pm|149}} || 1.263 ± 0.032 || 1.275 ± 0.056 || -
|-
| {{nuclide|Pm|151}} || 0.776 ± 0.018 || 0.796 ± 0.037 || -
|-
| {{nuclide|Sm|148}} || 0.0000168 ± 0.0000046 || 0.000039 ± 0.000011 || -
|-
| {{nuclide|Sm|150}} || 0.00227 ± 0.00078 || 0.0051 ± 0.0019 || -
|-
| {{nuclide|Sm|151}} || 0.776 ± 0.018 || 0.797 ± 0.037 || -
|-
| {{nuclide|Sm|153}} || 0.38 ± 0.03 || 0.4 ± 0.18 || -
|-
| {{nuclide|Eu|151}} || 0.776 ± 0.018 || 0.797 ± 0.037 || -
|-
| {{nuclide|Eu|152}} || 0.000000195 ± 0.00000005 || 0.00000048 ± 0.00000014 || -
|-
| {{nuclide|Eu|154}} || 0.000049 ± 0.000012 || 0.000127 ± 0.000043 || -
|-
| {{nuclide|Eu|155}} || 0.174 ± 0.03 || 0.171 ± 0.054 || -
|}
<!-- references for IAEA table C3 -->
{| class="wikitable"
|-
| style="width:12em;" | JEFF-3.1
| style="width:60em;" |
Joint 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, {{ISBN|92-64-02314-3}}.
|}

[[Image:fission yield.png|thumb|450px|Yields at 10<sup>0,1,2,3</sup> years after [[nuclear fission|fission]], probably of [[Pu-239]] not [[uranium-235|U-235]] because left hump is shifted right, not considering later [[neutron capture]], fraction of 100% not 200%. [[Beta decay]] [[Kr-85]]→[[rubidium|Rb]], [[Sr-90]]→[[zirconium|Zr]], [[Ru-106]]→[[palladium|Pd]], [[Sb-125]]→[[tellurium|Te]], [[Cs-137]]→[[barium|Ba]], [[Ce-144]]→[[neodymium|Nd]], [[Sm-151]]→[[europium|Eu]], [[Eu-155]]→[[gadolinium|Gd]] visible.]]

==Ordered by mass number==
Decays, even if lengthy, are given down to the stable nuclide.

Decays with half lives longer than a century are marked with a single asterisk ({{asterisk}}), while decays with a half life longer than a hundred million  years are marked with two asterisks ({{asterisk}}{{asterisk}}). 
{| class="wikitable sortable"
! Yield !! Isotope
|-
| 0.0508% || style="background:{{element color|p-block}}" | [[selenium-79]][[beta decay|→]]* || style="background:{{element color|p-block}}" | [[bromine-79]]
|-
| 0.2717% || style="background:{{element color|p-block}}" | [[krypton-85]][[beta decay|→]] || style="background:{{element color|s-block}}" | [[rubidium-85]]
|-
| 5.7518% || style="background:{{element color|s-block}}" | [[strontium-90]] [[beta decay|→]] || style="background:{{element color|d-block}}" | [[yttrium-90]][[beta decay|→]] || style="background:{{element color|d-block}}" | [[zirconium-90]]
|-
| 6.2956% || style="background:{{element color|d-block}}" | [[zirconium-93]] [[beta decay|→]]* || style="background:{{element color|d-block}}" | [[niobium-93]]
|-
| 6.0507% || style="background:{{element color|d-block}}" | [[technetium-99]][[beta decay|→]]* || style="background:{{element color|d-block}}" | [[ruthenium-99]]
|-
| 0.3912% || style="background:{{element color|d-block}}" | [[ruthenium-106]][[beta decay|→]] || style="background:{{element color|d-block}}" | [[rhodium-106]][[beta decay|→]] || style="background:{{element color|d-block}}" | [[palladium-106]]
|-
| 0.1629% || style="background:{{element color|d-block}}" | [[palladium-107]][[beta decay|→]]* || style="background:{{element color|d-block}}" | [[silver-107]]
|-
| 0.0003% || style="background:{{element color|d-block}}" | [[cadmium-113m]][[isomeric transition|→]] || style="background:{{element color|d-block}}" | [[cadmium-113]] (essentially stable)[[beta decay|→]]** || style="background:{{element color|p-block}}" | [[indium-113]]
|-
| 0.0297% || style="background:{{element color|p-block}}" | [[antimony-125]][[beta decay|→]] || style="background:{{element color|p-block}}" | [[tellurium-125m]][[isomeric transition|→]] || style="background:{{element color|p-block}}" | [[tellurium-125]]
|-
| 0.0236% || style="background:{{element color|p-block}}" | [[tin-126]] [[beta decay|→]]* || style="background:{{element color|p-block}}" | [[antimony-126]][[beta decay|→]] || style="background:{{element color|p-block}}" | [[tellurium-126]]
|-
| 0.9%    || style="background:{{element color|p-block}}" | [[iodine-129]][[beta decay|→]]* || style="background:{{element color|p-block}}" | [[xenon-129]]
|-
| 2.8336% || style="background:{{element color|p-block}}" | [[iodine-131]][[beta decay|→]] || style="background:{{element color|p-block}}" | [[xenon-131]]
|-
| 6.7896% || style="background:{{element color|s-block}}" | [[caesium-133]] [[neutron capture|→]] || style="background:{{element color|s-block}}" | [[caesium-134]][[beta decay|→]] || style="background:{{element color|s-block}}" | [[barium-134]]
|-
| 6.3333% || style="background:{{element color|p-block}}" | [[iodine-135]] [[beta decay|→]] || style="background:{{element color|p-block}}" | [[xenon-135]] [[beta decay|→]] || style="background:{{element color|s-block}}" | [[caesium-135]][[beta decay|→]]* || style="background:{{element color|s-block}}" | [[barium-135]]
|-
| 6.3333% || style="background:{{element color|p-block}}" | [[iodine-135]] [[beta decay|→]] || style="background:{{element color|p-block}}" | [[xenon-135]] [[neutron capture|→]] || style="background:{{element color|p-block}}" | [[xenon-136]] (essentially stable)[[double beta decay|→]]** || style="background:{{element color|s-block}}" | [[barium-136]]
|-
| 6.0899% || style="background:{{element color|s-block}}" | [[caesium-137]][[beta decay|→]] || style="background:{{element color|s-block}}" | [[barium-137]]
|-
| 2.2713% || style="background:{{element color|f-block}}" | [[promethium-147]][[beta decay|→]] || style="background:{{element color|f-block}}" | [[samarium-147]][[alpha decay|→]]* || style="background:{{element color|f-block}}" | [[neodymium-143]]
|-
| 1.0888% || style="background:{{element color|f-block}}" | [[samarium-149]]
|-
| 0.4203% || style="background:{{element color|f-block}}" | [[samarium-151]]
|-
| 0.0330% || style="background:{{element color|f-block}}" | [[europium-155]] [[beta decay|→]] || style="background:{{element color|f-block}}" | [[gadolinium-155]]
|-
| 0.0065% || style="background:{{element color|f-block}}" | [[gadolinium-157]]
|}

==Half lives, decay modes, and branching fractions==

{| class="wikitable"
|+ Half-lives and decay branching fractions for fission products<ref name="IAEA-D1">{{cite web |title=Half-lives and decay branching fractions for activation products |url=https://www-nds.iaea.org/sgnucdat/d1.htm |website=www-nds.iaea.org |publisher=IAEA |access-date=11 November 2016}}</ref>
|-
! Nuclide !! Half-life !! Decay mode !! Branching fraction !! Source !! Notes
|-
| {{nuclide|Br|85}} || 2.9 ± 0.06 m || β<sup>−</sup> || 1.0 || <ref name="ENSDF">Evaluated Nuclear Structure Data File, http://www-nds.iaea.org/ensdf/, 26 January 2006.</ref> || {{efn|β{{sup|−}} decay branches of 0.9982 ± 0.0002 to Kr-85m and 0.0018 ± 0.0002 to Kr-85.}}
|-
| {{nuclide|Kr|85}} || 10.752 ± 0.023 y || β<sup>−</sup> || 1.0 || <ref name="BIPM-5">M.-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.</ref>
|-
| rowspan="2" | {{nuclide|Kr|85m}} || rowspan="2" | 4.48 ± 0.008 h || IT || 0.214 ± 0.005 || rowspan="2" | <ref name="ENSDF"/>
|-
| β<sup>−</sup> || 0.786 ± 0.005
|-
| {{nuclide|Sr|90}} || 28.8 ± 0.07 y || β<sup>−</sup> || 1.0 || <ref name="LNHB">Laboratoire National Henri Becquerel, Recommended Data, http://www.nucleide.org/DDEP_WG/DDEPdata.htm {{Webarchive|url=https://web.archive.org/web/20210213021408/http://www.nucleide.org/DDEP_WG/DDEPdata.htm |date=2021-02-13 }}, 16 January 2006.</ref>
|-
| {{nuclide|Zr|95}} || 64.032 ± 0.006 d || β<sup>−</sup> || 1.0 || <ref name="LNHB"/>
|-
| {{nuclide|Nb|94}} || (7.3 ± 0.9) × 10<sup>6</sup> d || β<sup>−</sup> || 1.0 || <ref name="IAEA-CRP-XG">M.-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, {{ISBN|92-0-113606-4}}.
</ref>
|-
| rowspan="2" | {{nuclide|Nb|95m}} || rowspan="2" | 3.61 ± 0.03 d || β<sup>−</sup> || 0.025 ± 0.001 || rowspan="2" | <ref name="LNHB"/> || rowspan="2" | {{efn|ENSDF branching fractions: 0.944 ± 0.007 for IT and 0.056 ± 0.007 for β{{sup|−}}.}}
|-
| IT || 0.975 ± 0.001
|-
| {{nuclide|Nb|95}} || 34.985 ± 0.012 d || β<sup>−</sup> || 1.0 || <ref name="IAEA-CRP-XG"/>
|-
| {{nuclide|Tc|99}} || (2.111 ± 0.012) × 10<sup>5</sup> y || β<sup>−</sup> || 1.0 || <ref name="ENSDF"/>
|-
| {{nuclide|Ru|103}} || 39.247 ± 0.013 d || β<sup>−</sup> || 1.0 || <ref name="IAEA-CRP-XG"/>
|-
| {{nuclide|Ru|106}} || 1.018 ± 0.005 y || β<sup>−</sup> || 1.0 || <ref name="IAEA-CRP-XG"/>
|-
| {{nuclide|Rh|106}} || 30.1 ± 0.3 s || β<sup>−</sup> || 1.0 || <ref name="IAEA-CRP-XG"/>
|-
| rowspan="2" | {{nuclide|Sn|121m}} || rowspan="2" | 55 ± 5 y || β<sup>−</sup> || 0.224 ± 0.02 || rowspan="2" | <ref name="ENSDF"/>
|-
| IT || 0.776 ± 0.02
|-
| rowspan="2" | {{nuclide|Sb|122}} || rowspan="2" | 2.7238 ± 0.0002 d || EC || 0.0241 ± 0.0012 || rowspan="2" | <ref name="ENSDF"/>
|-
| β<sup>−</sup> || 0.9759 ± 0.0012
|-
| {{nuclide|Sb|124}} || 60.2 ± 0.03 d || β<sup>−</sup> || 1.0 || <ref name="ENSDF"/>
|-
| {{nuclide|Sb|125}} || 2.7584 ± 0.0006 y || β<sup>−</sup> || 1.0 || <ref name="IAEA-CRP-XG"/>
|-
| {{nuclide|I|129}} || (5.89 ± 0.23) × 10<sup>9</sup> d || β<sup>−</sup> || 1.0 || <ref name="IAEA-CRP-XG"/>
|-
| {{nuclide|I|131}} || 8.0233 ± 0.0019 d || β<sup>−</sup> || 1.0 || <ref name="BIPM-5"/>
|-
| {{nuclide|I|133}} || 20.87 ± 0.08 h || β<sup>−</sup> || 1.0 || <ref name="LNHB"/> || {{efn|β{{sup|−}} decay branch of 0.0288 ± 0.0002 to Xe-133m.}}
|-
| {{nuclide|I|135}} || 6.57 ± 0.02 h || β<sup>−</sup> || 1.0 || <ref name="ENSDF"/>
|-
| {{nuclide|Xe|131m}} || 11.930 ± 0.016 d || IT || 1.0 || <ref name="BIPM-5"/>
|-
| {{nuclide|Xe|133}} || 5.243 ± 0.001 d || β<sup>−</sup> || 1.0 || <ref name="ENSDF"/>
|-
| {{nuclide|Xe|133m}} || 2.19 ± 0.01 d || IT || 1.0 || <ref name="ENSDF"/>
|-
| {{nuclide|Xe|135}} || 9.14 ± 0.02 h || β<sup>−</sup> || 1.0 || <ref name="ENSDF"/>
|-
| rowspan="2" | {{nuclide|Xe|135m}} || rowspan="2" | 15.29 ± 0.05 m || β<sup>−</sup> || 0.003 ± 0.003 || rowspan="2" | <ref name="ENSDF"/> || rowspan="2" | {{efn|Branching fractions were averaged from ENSDF database.}}
|-
| IT || 0.997 ± 0.003
|-
|rowspan="2"| {{nuclide|Cs|134}} || rowspan="2" | 2.063 ± 0.003 y || EC || 0.000003 ± 0.000001 || rowspan="2" | <ref name="IAEA-CRP-XG"/> || rowspan="2" | {{efn|Branching fractions were adopted from ENSDF database.}}
|-
| β<sup>−</sup> || 0.999997 ± 0.000001
|-
| {{nuclide|Cs|137}} || 30.05 ± 0.08 y || β<sup>−</sup> || 1.0 || <ref name="IAEA-CRP-XG"/>
|-
| {{nuclide|Ba|140}} || 12.753 ± 0.004 d || β<sup>−</sup> || 1.0 || <ref name="BIPM-5"/>
|-
| {{nuclide|La|140}} || 1.67850 ± 0.00017 d || β<sup>−</sup> || 1.0 || <ref name="BIPM-5"/>
|-
| {{nuclide|Ce|141}} || 32.508 ± 0.010 d || β<sup>−</sup> || 1.0 || <ref name="LNHB"/>
|-
| {{nuclide|Ce|144}} || 285.1 ± 0.6 d || β<sup>−</sup> || 1.0 || <ref name="IAEA-CRP-XG"/>
|-
| {{nuclide|Pr|144}} || 17.28 ± 0.05 m || β<sup>−</sup> || 1.0 || <ref name="ENSDF"/>
|-
| {{nuclide|Nd|147}} || 10.98 ± 0.01 d || β<sup>−</sup> || 1.0 || <ref name="ENSDF"/>
|-
| {{nuclide|Pm|147}} || 2.6234 ± 0.0002 y || β<sup>−</sup> || 1.0 || <ref name="ENSDF"/>
|-
| rowspan="2" | {{nuclide|Pm|148m}} || rowspan="2" | 41.29 ± 0.11 d || IT || 0.042 ± 0.007 || rowspan="2" | <ref name="ENSDF"/>
|-
| β<sup>−</sup> || 0.958 ± 0.007
|-
| {{nuclide|Pm|148}} || 5.368 ± 0.002 d || β<sup>−</sup> || 1.0 || <ref name="ENSDF"/>
|-
| {{nuclide|Pm|149}} || 2.2117 ± 0.0021 d || β<sup>−</sup> || 1.0 || <ref name="ENSDF"/>
|-
| {{nuclide|Pm|151}} || 1.1833 ± 0.0017 d || β<sup>−</sup> || 1.0 || <ref name="ENSDF"/>
|-
| {{nuclide|Sm|151}} || 90 ± 6 y || β<sup>−</sup> || 1.0 || <ref name="ENSDF"/>
|-
| {{nuclide|Sm|153}} || 1.938 ± 0.010 d || β<sup>−</sup> || 1.0 || <ref name="IAEA-CRP-XG"/>
|-
| rowspan="2" | {{nuclide|Eu|152}} || rowspan="2" | (4.941 ± 0.007) × 10<sup>3</sup> d || β<sup>−</sup> || 0.279 ± 0.003 || rowspan="2" | <ref name="IAEA-CRP-XG"/> || rowspan="2" | {{efn|name=LNHBadopted|Branching fractions were adopted from LNHB data.}}
|-
| EC || 0.721 ± 0.003
|-
| rowspan="2" | {{nuclide|Eu|154}} || rowspan="2" | (3.1381 ± 0.0014) × 10<sup>3</sup> d || EC || 0.00018 ± 0.00013 || rowspan="2" | <ref name="IAEA-CRP-XG"/> || rowspan="2" | {{efn|name=LNHBadopted}}
|-
| β<sup>−</sup> || 0.99982 ± 0.00013
|-
| {{nuclide|Eu|155}} || 4.753 ± 0.016 y || β<sup>−</sup> || 1.0 || <ref name="IAEA-CRP-XG"/>
|}
{{noteslist}}
<!--  comment out previous table
{| class="wikitable sortable"
! Yield !! Isotope !! Halflife !! Comment
|-
|  2.8336% || [[iodine-131|<sup>131</sup>I]] || 8.02 d || Important in nuclear explosions and accidents but not in cooled [[spent nuclear fuel]]
|-
|  0.3912% || [[ruthenium-106|<sup>106</sup>Ru]] || 373.6 d
|-
|  6.7896% || [[cesium-133|<sup>133</sup>Cs]] [[neutron capture|→]] [[cesium-134|<sup>134</sup>Cs]] || 2.065 y || [[neutron capture]] converts a few percent of nonradioactive <sup>133</sup>Cs to <sup>134</sup>Cs, which has low direct yield because [[beta decay]] stops at <sup>134</sup>Xe
|-
|  2.2713% || [[promethium-147|<sup>147</sup>Pm]] || 2.62 y
|-
|  0.0297% || [[antimony-125|<sup>125</sup>Sb]] || 2.76 y
|-
| <0.0330% || [[europium-155|<sup>155</sup>Eu]] [[beta decay|→]] [[gadolinium-155|<sup>155</sup>Gd]] || 4.76 y || both [[neutron poison]]s, most will be destroyed by [[neutron capture]] while still in reactor
|-
|  0.2717% || [[krypton-85|<sup>85</sup>Kr]] || 10.78 y || Current [[nuclear reprocessing]] releases it to atmosphere
|-
| <0.0003% || [[cadmium-113m|<sup>113m</sup>Cd]] || 14.1 y || most will be destroyed by [[neutron capture]] while still in reactor
|-
|  5.7518% || [[strontium-90|<sup>90</sup>Sr]] || 28.9 y || One of two principal medium-term radiation and heat sources
|-
|  6.0899% || [[Cs-137|<sup>137</sup>Cs]] || 30.17 y || One of two principal medium-term radiation and heat sources
|-
| <0.4203% || [[samarium-151|<sup>151</sup>Sm]] || 90 y || Most will be destroyed by [[neutron capture]] while still in reactor
|-
|  6.0507% || [[Tc-99|<sup>99</sup>Tc]] || 211 ky || Dominant radiation source among FP in period about {{e|4}} to {{e|6}} years; mobile in environment; candidate for disposal by [[nuclear transmutation]]
|-
|  0.0236% || [[tin-126|<sup>126</sup>Sn]] || 230 ky
|-
|  0.0508% || [[selenium-79|<sup>79</sup>Se]] || 327 ky
|-
|  6.2956% || [[Zr-93|<sup>93</sup>Zr]] || 1.53 My
|-
| <6.3333% || [[Cs-135|<sup>135</sup>Cs]] || 2.3 My
|-
|  0.1629% || [[palladium-107|<sup>107</sup>Pd]] || 6.5 My
|-
|  0.6576% || [[iodine-129|<sup>129</sup>I]] || 15.7 My || Mobile in environment; candidate for disposal by [[nuclear transmutation]]
|-
| <1.0888% || [[samarium-149|<sup>149</sup>Sm]] || nonradioactive || [[neutron poison]]
|-
| <0.0065% || [[gadolinium-157|<sup>157</sup>Gd]] || nonradioactive || [[neutron poison]]
|}
-->

==Ordered by thermal neutron absorption cross section==
{| class="wikitable sortable"
! Barns !! Yield !! Isotope !! ''t''<sub>½</sub> !! Comment
|-
|align=right| {{nts|2650000}} || 6.3333% || {{hs|iodine-135}} [[iodine-135|<sup>135</sup>I]] [[beta decay|→]] [[xenon-135|<sup>135</sup>Xe]] || {{ntsh|0.0006}} 6.57 h || Most important [[neutron poison]]; [[neutron capture]] rapidly converts <sup>135</sup>Xe to <sup>136</sup>Xe; remainder decays (9.14&nbsp;h) to [[Cs-135|<sup>135</sup>Cs]] (2.3&nbsp;My).
|-
|align=right| {{nts|254000}} || 0.0065% || {{hs|gadolinium}} [[gadolinium-157|<sup>157</sup>Gd]] || ∞ || [[Neutron poison]], but low yield.
|-
|align=right| {{nts|40140}} || 1.0888% || {{hs|samarium-149}} [[samarium-149|<sup>149</sup>Sm]] || ∞ || 2nd most important [[neutron poison]].
|-
|align=right| {{nts|20600}} || 0.0003% || {{hs|cadmium}} [[cadmium-113m|<sup>113m</sup>Cd]] || {{ntsh|14}} 14.1 y || Most will be destroyed by neutron capture.
|-
|align=right| {{nts|15200}} || 0.4203% || {{hs|samarium-151}} [[samarium-151|<sup>151</sup>Sm]] || {{ntsh|90}} 90 y || Most will be destroyed by neutron capture.
|-
|align=right| {{nts|3950}} <br/>60,900 || 0.0330% || {{hs|europium}} [[europium-155|<sup>155</sup>Eu]] [[beta decay|→]] [[gadolinium-155|<sup>155</sup>Gd]] || {{ntsh|5}} 4.76 y || Both [[neutron poison]]s.
|-
|align=right| {{nts|96}} || 2.2713% || {{hs|promethium}} [[promethium-147|<sup>147</sup>Pm]] || {{ntsh|2.6}} 2.62 y|| Suitable for [[radioisotope thermoelectric generator]]s with annual or semi-annual refueling.
|-
|align=right| {{nts|80}} || 2.8336% || {{hs|iodine-131}} [[iodine-131|<sup>131</sup>I]] || {{ntsh|0.008}} 8.02 d
|-
|align=right| {{nts|29}} <br/>140 || 6.7896% || {{hs|caesium-133}} [[caesium-133|<sup>133</sup>Cs]] [[neutron capture|→]] [[caesium-134|<sup>134</sup>Cs]] || ∞ <br/>2.065&nbsp;y || [[Neutron capture]] converts a few percent of nonradioactive <sup>133</sup>Cs to <sup>134</sup>Cs, which has very low direct yield because [[beta decay]] stops at <sup>134</sup>Xe; further capture will add to long-lived <sup>135</sup>Cs.
|-
|align=right| {{nts|20}} || 6.0507% || {{hs|technetium}} [[Tc-99|<sup>99</sup>Tc]] || {{ntsh|211000}} 211 ky || Candidate for disposal by [[nuclear transmutation]].
|-
|align=right| {{nts|18}} || 0.6576% || {{hs|iodine-129}} [[iodine-129|<sup>129</sup>I]] || {{ntsh|15700000}} 15.7&nbsp;My || Candidate for disposal by [[nuclear transmutation]].
|-
|align=right| {{nts|2.7}} || 6.2956% || {{hs|zirconium}} [[Zr-93|<sup>93</sup>Zr]] || {{ntsh|1530000}} 1.53&nbsp;My || Transmutation impractical.
|-
|align=right| {{nts|1.8}} || 0.1629% || {{hs|palladium}} [[palladium-107|<sup>107</sup>Pd]] || {{ntsh|6500000}} 6.5 My
|-
|align=right| {{nts|1.66}} || 0.2717% || {{hs|krypton}} [[krypton-85|<sup>85</sup>Kr]] || {{ntsh|11}} 10.78 y
|-
|align=right| {{nts|0.90}} || 5.7518% || {{hs|strontium}} [[strontium-90|<sup>90</sup>Sr]] || {{ntsh|29}} 28.9 y
|-
|align=right| {{nts|0.15}} || 0.3912% || {{hs|ruthenium}} [[ruthenium-106|<sup>106</sup>Ru]] || {{ntsh|1}} 373.6&nbsp;d
|-
|align=right| {{nts|0.11}} || 6.0899% || {{hs|caesium-137}} [[Cs-137|<sup>137</sup>Cs]] || {{ntsh|30}} 30.17 y
|-
| || 0.0297% || {{hs|antimony}} [[antimony-125|<sup>125</sup>Sb]] || {{ntsh|2.7}} 2.76 y
|-
| || 0.0236% || {{hs|tin}} [[tin-126|<sup>126</sup>Sn]] || {{ntsh|230000}} 230 ky
|-
| || 0.0508% || {{hs|selenium}} [[selenium-79|<sup>79</sup>Se]] || {{ntsh|327000}} 327 ky
|-
|}

==References==
<references />

==External links==
* [https://www-nds.iaea.org/sgnucdat/safeg2008.pdf HANDBOOK OF NUCLEAR DATA FOR SAFEGUARDS: DATABASE EXTENSIONS, AUGUST 2008]
* [[Image:Ndslivechart.png]] '''[http://www-nds.iaea.org/livechart The Live Chart of Nuclides - IAEA ]''' Color-map of yields, and detailed data by click on a nuclide.

[[Category:Nuclear fission]]
[[Category:Nuclear chemistry]]