Activation product

Last updated

An activation product is a material that has been made radioactive by the process of neutron activation.

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. All of these, however, need to be handled as radioactive waste. Some nuclides originate in more than one way, as activation products or fission products.

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.

Activation product radionuclides include:

Half-lives and decay branching fractions for activation products [1]
NuclideHalf-lifeDecay modebranching fractionSourceNotes
3
1
H
12.312 ± 0.025 yβ1.0LNHB
10
4
Be
( 1.51 ± 0.06 ) x 106 yβ1.0ENSDF
14
6
C
( 5.7 ± 0.03 ) x 103 yβ1.0LNHB
15
6
C
2.449 ± 0.005 sβ1.0ENSDF
16
7
N
7.13 ± 0.02 sβ1.0ENSDF
19
8
O
26.88 ± 0.05 sβ1.0ENSDF
22
11
Na
950.57 ± 0.23 dEC0.1011 ± 0.0002aIAEA-CRP-XG[1]
β+0.8989 ± 0.0002a
24
11
Na
0.62329 ± 0.00006 dβ1.0IAEA-CRP-XG
27
12
Mg
9.458 ± 0.012 mβ1.0ENSDF
26
13
Al
( 7.17 ± 0.24 ) x 105 yEC0.1825 ± 0.0023bLNHB[2]
β+0.8175 ± 0.0023b
35
16
S
87.32 ± 0.16 dβ1.0LNHB
36
17
Cl
( 0.01 ± 0.03 ) x 105 yEC0.019 ± 0.001LNHB
β0.981 ± 0.001
39
18
Ar
269 ± 3 yβ1.0ENSDF
41
18
Ar
109.61 ± 0.04 mβ1.0ENSDF
40
19
K
( 4.563 ± 0.013 ) x 1011 dEC0.1086 ± 0.0013aIAEA-CRP-XG[1]
β0.8914 ± 0.0013a
42
19
K
12.36 ± 0.012 hβ1.0ENSDF
41
20
Ca
( 1.02 ± 0.07 ) x 105 yEC1.0ENSDF
45
20
Ca
162.61 ± 0.09 dβ1.0ENSDF
47
21
Sc
3.3492 ± 0.0006 dβ1.0ENSDF
48
21
Sc
43.67 ± 0.09 hβ1.0ENSDF
51
24
Cr
27.7009 ± 0.002 dEC1.0IAEA-CRP-XG
54
25
Mn
312.29 ± 0.26 dEC1.0IAEA-CRP-XG
56
25
Mn
0.107449 ± 0.000019 dβ1.0IAEA-CRP-XG
55
26
Fe
( 1.0027 ± 0.0023 ) x 103 dEC1.0IAEA-CRP-XG
59
26
Fe
44.494 ± 0.013 dβ1.0IAEA-CRP-XG
57
27
Co
271.8 ± 0.05 dEC1.0IAEA-CRP-XG
58
27
Co
70.86 ± 0.06 dβ+0.15 ± 0.0020aIAEA-CRP-XG[1]
EC0.85 ± 0.0020a
60
27
Co
( 1.92523 ± 0.00027 ) x 103 dβ1.0IAEA-CRP-XG
59
28
Ni
( 7.6 ± 0.5 ) x 104 yEC1.0ENSDF
63
28
Ni
98.7 ± 2.4 yβ1.0LNHB
65
28
Ni
2.51719 ± 0.00026 hβ1.0ENSDF
64
29
Cu
0.52929 ± 0.00018 dβ+0.179 ± 0.002aIAEA-CRP-XG[1]
β0.39 ± 0.003a
EC0.431 ± 0.005a
66
29
Cu
5.12 ± 0.014 mβ1.0ENSDF
65
30
Zn
243.86 ± 0.2 dβ+0.0142 ± 0.0001aIAEA-CRP-XG[1]
EC0.9858 ± 0.0001a
93m
41
Nb
( 5.73 ± 0.22 ) x 103 dIT1.0IAEA-CRP-XG
93
42
Mo
( 4.0 ± 0.8 ) x 103 yEC1.0ENSDF
99m
43
Tc
0.250281 ± 0.000022 dβ0.000037 ± 0.000006aIAEA-CRP-XG[1]
IT0.999963 ± 0.000006a
110m
47
Ag
249.85 ± 0.1 dIT0.0136 ± 0.0008aIAEA-CRP-XG[1]
β0.9864 ± 0.0008a
115m
49
In
4.486 ± 0.004 hβ0.05 ± 0.008ENSDF
IT0.95 ± 0.008
126
53
I
12.93 ± 0.05 dβ0.473 ± 0.006ENSDF
EC0.527 ± 0.006
175
72
Hf
70 ± 2 dEC1.0ENSDF
181
72
Hf
42.39 ± 0.06 dβ1.0ENSDF
182
73
Ta
114.43 ± 0.04 dβ1.0ENSDF
181
74
W
121.2 ± 0.2 dEC1.0ENSDF
185
74
W
75.1 ± 0.3 dβ1.0ENSDF
187
74
W
23.72 ± 0.06 hβ1.0ENSDF
198
79
Au
2.695 ± 0.0007 dβ1.0IAEA-CRP-XG
197
80
Hg
64.14 ± 0.05 hEC1.0ENSDF
203
80
Hg
46.594 ± 0.012 dβ1.0IAEA-CRP-XG
LNHBLaboratoire National Henri Becquerel, Recommended Data, http://www.nucleide.org/DDEP_WG/DDEPdata.htm Archived 2021-02-13 at the Wayback Machine , 5 June 2008.
IAEA-CRP-XGM.-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.
ENSDFEvaluated 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..


Related Research Articles

<span class="mw-page-title-main">Nuclear fission</span> Nuclear reaction splitting an atom into multiple parts

Nuclear fission is a reaction in which the nucleus of an atom splits into two or more smaller nuclei. The fission process often produces gamma photons, and releases a very large amount of energy even by the energetic standards of radioactive decay.

<span class="mw-page-title-main">Nuclear reactor</span> Device used to initiate and control a nuclear chain reaction

A nuclear reactor is a device used to initiate and control a fission nuclear chain reaction or nuclear fusion reactions. Nuclear reactors are used at nuclear power plants for electricity generation and in nuclear marine propulsion. Heat from nuclear fission is passed to a working fluid, which in turn runs through steam turbines. These either drive a ship's propellers or turn electrical generators' shafts. Nuclear generated steam in principle can be used for industrial process heat or for district heating. Some reactors are used to produce isotopes for medical and industrial use, or for production of weapons-grade plutonium. As of 2022, the International Atomic Energy Agency reports there are 422 nuclear power reactors and 223 nuclear research reactors in operation around the world.

<span class="mw-page-title-main">Nuclear fuel cycle</span> Process of manufacturing and consuming nuclear fuel

The nuclear fuel cycle, also called nuclear fuel chain, is the progression of nuclear fuel through a series of differing stages. It consists of steps in the front end, which are the preparation of the fuel, steps in the service period in which the fuel is used during reactor operation, and steps in the back end, which are necessary to safely manage, contain, and either reprocess or dispose of spent nuclear fuel. If spent fuel is not reprocessed, the fuel cycle is referred to as an open fuel cycle ; if the spent fuel is reprocessed, it is referred to as a closed fuel cycle.

<span class="mw-page-title-main">Breeder reactor</span> Nuclear reactor generating more fissile material than it consumes

A breeder reactor is a nuclear reactor that generates more fissile material than it consumes. These reactors can be fuelled with more commonly available isotopes of uranium and thorium, such as uranium-238 or thorium-232, as opposed to the rare uranium-235 which is used in conventional reactors. These materials are called fertile materials since they can be bred into fuel by these breeder reactors.

<span class="mw-page-title-main">Neutron emission</span> Type of radioactive decay

Neutron emission is a mode of radioactive decay in which one or more neutrons are ejected from a nucleus. It occurs in the most neutron-rich/proton-deficient nuclides, and also from excited states of other nuclides as in photoneutron emission and beta-delayed neutron emission. As only a neutron is lost by this process the number of protons remains unchanged, and an atom does not become an atom of a different element, but a different isotope of the same element.

<span class="mw-page-title-main">Nuclear fission product</span> Atoms or particles produced by nuclear fission

Nuclear fission products are the atomic fragments left after a large atomic nucleus undergoes nuclear fission. Typically, a large nucleus like that of uranium fissions by splitting into two smaller nuclei, along with a few neutrons, the release of heat energy, and gamma rays. The two smaller nuclei are the fission products..

<span class="mw-page-title-main">Fast-neutron reactor</span> Nuclear reactor where fast neutrons maintain a fission chain reaction

A fast-neutron reactor (FNR) or fast-spectrum reactor or simply a fast reactor is a category of nuclear reactor in which the fission chain reaction is sustained by fast neutrons, as opposed to slow thermal neutrons used in thermal-neutron reactors. Such a fast reactor needs no neutron moderator, but requires fuel that is relatively rich in fissile material when compared to that required for a thermal-neutron reactor. Around 20 land based fast reactors have been built, accumulating over 400 reactor years of operation globally. The largest of this was the Superphénix Sodium cooled fast reactor in France that was designed to deliver 1,242 MWe. Fast reactors have been intensely studied since the 1950s, as they provide certain decisive advantages over the existing fleet of water cooled and water moderated reactors. These are:

A subcritical reactor is a nuclear fission reactor concept that produces fission without achieving criticality. Instead of sustaining a chain reaction, a subcritical reactor uses additional neutrons from an outside source. There are two general classes of such devices. One uses neutrons provided by a nuclear fusion machine, a concept known as a fusion–fission hybrid. The other uses neutrons created through spallation of heavy nuclei by charged particles such as protons accelerated by a particle accelerator, a concept known as an accelerator-driven system (ADS) or accelerator-driven sub-critical reactor.

<span class="mw-page-title-main">Integral fast reactor</span> Nuclear reactor design

The integral fast reactor is a design for a nuclear reactor using fast neutrons and no neutron moderator. IFR would breed more fuel and is distinguished by a nuclear fuel cycle that uses reprocessing via electrorefining at the reactor site.

<span class="mw-page-title-main">Decay heat</span> Heat generated from radioactive decay

Decay heat is the heat released as a result of radioactive decay. This heat is produced as an effect of radiation on materials: the energy of the alpha, beta or gamma radiation is converted into the thermal movement of atoms.

<span class="mw-page-title-main">Neutron activation</span> Induction of radioactivity by neutron radiation

Neutron activation is the process in which neutron radiation induces radioactivity in materials, and occurs when atomic nuclei capture free neutrons, becoming heavier and entering excited states. The excited nucleus decays immediately by emitting gamma rays, or particles such as beta particles, alpha particles, fission products, and neutrons. Thus, the process of neutron capture, even after any intermediate decay, often results in the formation of an unstable activation product. Such radioactive nuclei can exhibit half-lives ranging from small fractions of a second to many years.

<span class="mw-page-title-main">Nuclear fuel</span> Material used in nuclear power stations

Nuclear fuel is material used in nuclear power stations to produce heat to power turbines. Heat is created when nuclear fuel undergoes nuclear fission.

Caesium (55Cs) has 40 known isotopes, making it, along with barium and mercury, one of the elements with the most isotopes. The atomic masses of these isotopes range from 112 to 151. Only one isotope, 133Cs, is stable. The longest-lived radioisotopes are 135Cs with a half-life of 2.3 million years, 137
Cs
with a half-life of 30.1671 years and 134Cs with a half-life of 2.0652 years. All other isotopes have half-lives less than 2 weeks, most under an hour.

In applications such as nuclear reactors, a neutron poison is a substance with a large neutron absorption cross-section. In such applications, absorbing neutrons is normally an undesirable effect. However, neutron-absorbing materials, also called poisons, are intentionally inserted into some types of reactors in order to lower the high reactivity of their initial fresh fuel load. Some of these poisons deplete as they absorb neutrons during reactor operation, while others remain relatively constant.

<span class="mw-page-title-main">Spent nuclear fuel</span> Nuclear fuel thats been irradiated in a nuclear reactor

Spent nuclear fuel, occasionally called used nuclear fuel, is nuclear fuel that has been irradiated in a nuclear reactor. It is no longer useful in sustaining a nuclear reaction in an ordinary thermal reactor and, depending on its point along the nuclear fuel cycle, it will have different isotopic constituents than when it started.

<span class="mw-page-title-main">Fission products (by element)</span> Breakdown of nuclear fission results

This page discusses each of the main elements in the mixture of fission products produced by nuclear fission of the common nuclear fuels uranium and plutonium. The isotopes are listed by element, in order by atomic number.

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.

Long-lived fission products (LLFPs) are radioactive materials with a long half-life produced by nuclear fission of uranium and plutonium. Because of their persistent radiotoxicity, it is necessary to isolate them from humans and the biosphere and to confine them in nuclear waste repositories for geological periods of time.

<span class="mw-page-title-main">Liquid fluoride thorium reactor</span> Type of nuclear reactor that uses molten material as fuel

The liquid fluoride thorium reactor is a type of molten salt reactor. LFTRs use the thorium fuel cycle with a fluoride-based molten (liquid) salt for fuel. In a typical design, the liquid is pumped between a critical core and an external heat exchanger where the heat is transferred to a nonradioactive secondary salt. The secondary salt then transfers its heat to a steam turbine or closed-cycle gas turbine.

<span class="mw-page-title-main">Nuclear transmutation</span> Conversion of an atom from one element to another

Nuclear transmutation is the conversion of one chemical element or an isotope into another chemical element. Nuclear transmutation occurs in any process where the number of protons or neutrons in the nucleus of an atom is changed.

References

  1. "Half-lives and decay branching fractions for activation products". www-nds.iaea.org. IAEA. Retrieved 11 November 2016.