Activation product

{{Short description|Materials made radioactive by neutron activation}}

An '''activation product''' is a material that has been made radioactive by the process of neutron activation. ==Process== Fission products and actinides produced by neutron absorption of nuclear fuel itself are normally referred to by those specific names, and ''activation product'' reserved for products of neutron capture by other materials, such as structural components of the nuclear reactor or nuclear bomb, the reactor coolant, control rods or other neutron poisons, or materials in the environment. In these cases their production is undesired and they need to be handled as radioactive waste. Some nuclides can be produced both as activation products or as fission products. For example molybdenum-99 which is an important nuclide in "molybdenum cows" used in medical diagnostics can be produced either by fissioning ²³⁵U or by neutron irradiation of ⁹⁸Mo.<ref>{{cite journal | last1=Hasan | first1=Shameem | last2=Prelas | first2=Mark A. | title=Molybdenum-99 production pathways and the sorbents for 99Mo/99mTc generator systems using (N, γ) 99Mo: A review | journal=SN Applied Sciences | date=2020 | volume=2 | issue=11 | article-number=1782 | doi=10.1007/s42452-020-03524-1 | url=https://link.springer.com/article/10.1007/s42452-020-03524-1 }}</ref> ==Practical uses== However, neutron activation (usually in a dedicated research reactor, but sometimes also in power reactors like the CANDUs at Bruce nuclear generating station<ref>{{cite web | title=Isotopes and Medical Innovation | url=https://www.brucepower.com/isotopes-and-medical-innovation/ }}</ref><ref>{{cite web | title=Ottawa, Bruce Power detail plans to expand medical isotope production | work=The Globe and Mail | date=19 August 2025 | url=https://www.theglobeandmail.com/business/article-ottawa-bruce-power-expand-medical-isotope-production/ }}</ref><ref>{{cite web | title=Bruce completes largest-to-date radioisotope delivery | date=24 November 2023 | url=https://www.world-nuclear-news.org/Articles/Bruce-completes-largest-to-date-radioisotope-deliv }}</ref>) is also used deliberately to produce desired radioisotopes for uses in food irradiation, nuclear medicine and to sterilize equipment via gamma radiation emitted from isotopes such as Cobalt-60.<ref>{{cite web | title=Cobalt-60: A Sustainable Sterilization Method | url=https://www.nordion.com/cobalt-60/a-sustainable-sterilization-method/ }}</ref>

Activation products in a reactor's primary coolant loop are a main reason reactors use a chain of two or even three coolant loops linked by heat exchangers.

Fusion reactors will not produce radioactive waste from the fusion product nuclei themselves, which are normally just helium-4, but generate high neutron fluxes, so activation products are a particular concern. ==List of activation products== Activation product radionuclides include:

{| class="wikitable" |+ Half-lives and decay branching fractions for activation 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|H|3}}||12.312 ± 0.025 y||β⁻||1.0||LNHB |- |{{nuclide|Be|10}}||( 1.51 ± 0.06 ) × 10⁶ y||β⁻||1.0||ENSDF |- |{{nuclide|C|14}}||( 5.7 ± 0.03 ) × 10³ y||β⁻||1.0||LNHB |- |{{nuclide|C|15}}||2.449 ± 0.005 s||β⁻||1.0||ENSDF |- |{{nuclide|N|16}}||7.13 ± 0.02 s||β⁻||1.0||ENSDF |- |{{nuclide|O|19}}||26.88 ± 0.05 s||β⁻||1.0||ENSDF |- |rowspan="2"|{{nuclide|Na|22}}||rowspan="2"|950.57 ± 0.23 d||EC||0.1011 ± 0.0002a||rowspan="2"|IAEA-CRP-XG||rowspan="2"|[1] |- ||β⁺||0.8989 ± 0.0002a |- |{{nuclide|Na|24}}||0.62329 ± 0.00006 d||β⁻||1.0||IAEA-CRP-XG |- |{{nuclide|Mg|27}}||9.458 ± 0.012 m||β⁻||1.0||ENSDF |- |rowspan="2"|{{nuclide|Al|26}}||rowspan="2"|( 7.17 ± 0.24 ) × 10⁵ y||EC||0.1825 ± 0.0023b||rowspan="2"|LNHB||rowspan="2"|[2] |- ||β⁺||0.8175 ± 0.0023b |- |{{nuclide|S|35}}||87.32 ± 0.16 d||β⁻||1.0||LNHB |- |rowspan="2"|{{nuclide|Cl|36}}||rowspan="2"|( 0.01 ± 0.03 ) × 10⁵ y||EC||0.019 ± 0.001||rowspan="2"|LNHB |- ||β⁻||0.981 ± 0.001 |- |{{nuclide|Ar|39}}||269 ± 3 y||β⁻||1.0||ENSDF |- |{{nuclide|Ar|41}}||109.61 ± 0.04 m||β⁻||1.0||ENSDF |- |rowspan="2"|{{nuclide|K|40}}||rowspan="2"|( 4.563 ± 0.013 ) × 10¹¹ d||EC||0.1086 ± 0.0013a||rowspan="2"|IAEA-CRP-XG||rowspan="2"|[1] |- ||β⁻||0.8914 ± 0.0013a |- |{{nuclide|K|42}}||12.36 ± 0.012 h||β⁻||1.0||ENSDF |- |{{nuclide|Ca|41}}||( 1.02 ± 0.07 ) × 10⁵ y||EC||1.0||ENSDF |- |{{nuclide|Ca|45}}||162.61 ± 0.09 d||β⁻||1.0||ENSDF |- |{{nuclide|Sc|47}}||3.3492 ± 0.0006 d||β⁻||1.0||ENSDF |- |{{nuclide|Sc|48}}||43.67 ± 0.09 h||β⁻||1.0||ENSDF |- |{{nuclide|Cr|51}}||27.7009 ± 0.002 d||EC||1.0||IAEA-CRP-XG |- |{{nuclide|Mn|54}}||312.29 ± 0.26 d||EC||1.0||IAEA-CRP-XG |- |{{nuclide|Mn|56}}||0.107449 ± 0.000019 d||β⁻||1.0||IAEA-CRP-XG |- |{{nuclide|Fe|55}}||( 1.0027 ± 0.0023 ) × 10³ d||EC||1.0||IAEA-CRP-XG |- |{{nuclide|Fe|59}}||44.494 ± 0.013 d||β⁻||1.0||IAEA-CRP-XG |- |{{nuclide|Co|57}}||271.8 ± 0.05 d||EC||1.0||IAEA-CRP-XG |- |rowspan="2"|{{nuclide|Co|58}}||rowspan="2"|70.86 ± 0.06 d||β⁺||0.15 ± 0.0020a||rowspan="2"|IAEA-CRP-XG||rowspan="2"|[1] |- ||EC||0.85 ± 0.0020a |- |{{nuclide|Co|60}}||( 1.92523 ± 0.00027 ) × 10³ d||β⁻||1.0||IAEA-CRP-XG |- |{{nuclide|Ni|59}}||( 7.6 ± 0.5 ) × 10⁴ y||EC||1.0||ENSDF |- |{{nuclide|Ni|63}}||98.7 ± 2.4 y||β⁻||1.0||LNHB |- |{{nuclide|Ni|65}}||2.51719 ± 0.00026 h||β⁻||1.0||ENSDF |- |rowspan="3"|{{nuclide|Cu|64}}||rowspan="3"|0.52929 ± 0.00018 d||β⁺||0.179 ± 0.002a||rowspan="3"|IAEA-CRP-XG||rowspan="3"|[1] |- ||β⁻||0.39 ± 0.003a |- ||EC||0.431 ± 0.005a |- |{{nuclide|Cu|66}}||5.12 ± 0.014 m||β⁻||1.0||ENSDF |- |rowspan="2"|{{nuclide|Zn|65}}||rowspan="2"|243.86 ± 0.2 d||β⁺||0.0142 ± 0.0001a||rowspan="2"|IAEA-CRP-XG||rowspan="2"|[1] |- ||EC||0.9858 ± 0.0001a |- |{{nuclide|Nb|93m}}||( 5.73 ± 0.22 ) × 10³ d||IT||1.0||IAEA-CRP-XG |- |{{nuclide|Mo|93}}||( 4.0 ± 0.8 ) × 10³ y||EC||1.0||ENSDF |- |rowspan="2"|{{nuclide|Tc|99m}}||rowspan="2"|0.250281 ± 0.000022 d||β⁻||0.000037 ± 0.000006a||rowspan="2"|IAEA-CRP-XG||rowspan="2"|[1] |- ||IT||0.999963 ± 0.000006a |- |rowspan="2"|{{nuclide|Ag|110m}}||rowspan="2"|249.85 ± 0.1 d||IT||0.0136 ± 0.0008a||rowspan="2"|IAEA-CRP-XG||rowspan="2"|[1] |- ||β⁻||0.9864 ± 0.0008a |- |rowspan="2"|{{nuclide|In|115m}}||rowspan="2"|4.486 ± 0.004 h||β⁻||0.05 ± 0.008||rowspan="2"|ENSDF |- ||IT||0.95 ± 0.008 |- |rowspan="2"|{{nuclide|I|126}}||rowspan="2"|12.93 ± 0.05 d||β⁻||0.473 ± 0.006||rowspan="2"|ENSDF |- ||EC||0.527 ± 0.006 |- |{{nuclide|Hf|175}}||70 ± 2 d||EC||1.0||ENSDF |- |{{nuclide|Hf|181}}||42.39 ± 0.06 d||β⁻||1.0||ENSDF |- |{{nuclide|Ta|182}}||114.43 ± 0.04 d||β⁻||1.0||ENSDF |- |{{nuclide|W|181}}||121.2 ± 0.2 d||EC||1.0||ENSDF |- |{{nuclide|W|185}}||75.1 ± 0.3 d||β⁻||1.0||ENSDF |- |{{nuclide|W|187}}||23.72 ± 0.06 h||β⁻||1.0||ENSDF |- |{{nuclide|Au|198}}||2.695 ± 0.0007 d||β⁻||1.0||IAEA-CRP-XG |- |{{nuclide|Hg|197}}||64.14 ± 0.05 h||EC||1.0||ENSDF |- |{{nuclide|Hg|203}}||46.594 ± 0.012 d||β⁻||1.0||IAEA-CRP-XG |}

<!-- references for IAEA table D1 --> {| class="wikitable" |- | 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 }}, 5 June 2008. |- | style="width: 12em;"| IAEA-CRP-XG | style="width: 60em;"| M.-M. Bé, V.P. Chechev, R. Dersch, O.A.M. Helene, R.G. Helmer, M. Herman, S. Hlav ác, 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}}. |- | ENSDF | Evaluated Nuclear Structure Data File, http://www-nds.iaea.org/ensdf/, 5 June 2008. |}

[1] Branching fractions from LNHB database.

[2] Branching fractions renormalised to sum to 1.0..

<!-- old table {| class="wikitable sortable" !Nuclide||See also||Halflife<br>(years)||Parent |- |Tritium|| || 12.3 ||Lithium-6,7<br>Boron-10<br>Deuterium |- |Beryllium-10|| || 1,530,000 ||Boron-10 |- |Carbon-14|| || 5,730 || Nitrogen-14<br>Carbon-13 |- |Sodium-24||Fast breeder|| 0.0017 ||Sodium-23 |- |Sulfur-35|| || 0.24 ||Chlorine-35 1% branch |- |Chlorine-36|| || 301,000 ||Chlorine-35 |- |Argon-39|| || 269 ||Argon-38 |- |Iron-55|| || 2.73 ||Iron-54 |- |Nickel-59|| || 76,000 ||Nickel-58 |- |Cobalt-60|| || 5.27 ||Cobalt-59 |- |Nickel-63|| || 100 ||Nickel-62 |- |Molybdenum-93|| || 4,000 || Molybdenum-92 |- |Niobium-93m|| || 16 |- |Niobium-94|| || 20,300 ||Niobium-93 |- |Technetium-99||LLFP||211,000||Molybdenum-98 |- |Silver-108m|| || 418 ||Silver-107 |- |Cadmium-113m|| || 13 ||Cadmium-112 |- |Tin-121m||[https://web.archive.org/web/20070715135738/http://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr6567/cr6567.pdf]|| 56 ||Tin-120 |- |Lead-205|| Q=51&nbsp;keV|| 15,300,000 || Lead-204 |- |Polonium-210||Lead-bismuth eutectic|| 0.379 ||Bismuth-209 |} -->

==References== {{Reflist}}

==External links== * [http://www-nds.iaea.org/reports-new/tecdocs/technical-reports-series-156.pdf Handbook on Nuclear Activation Cross-Sections, IAEA, 1974] * [http://www.nndc.bnl.gov/databases/databases.html Nuclear Structure and Decay Databases (nndc.bnl.gov)] {{Webarchive|url=https://web.archive.org/web/20130320225323/http://www.nndc.bnl.gov/databases/databases.html |date=2013-03-20 }} * [http://physics.nist.gov/PhysRefData/Halflife/halflife.html New and revised half-life measurements results made by the Radioactivity Group of NIST] * [https://www-nds.iaea.org/sgnucdat/safeg2008.pdf HANDBOOK OF NUCLEAR DATA FOR SAFEGUARDS: DATABASE EXTENSIONS, AUGUST 2008]

Category:Radiation Category:Neutron Category:Radiation effects Category:Nuclear materials