Просмотр кода страницы Английская Википедия:Fission product yield

{{Английская Википедия/Панель перехода}}
{{Short description|Fractions of products of nuclear fission}}
{{main|Nuclear fission product}}
<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 greater is stable and does not 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%. Less often, it is stated as percentage of all fission products, so that the percentages sum to 100%. [[Ternary fission]], about 0.2–0.4% of fissions, also produces a third light nucleus such as [[helium-4]] (90%) or [[tritium]] (7%).

== 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]][[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, 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]]
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