المعرفة

عائد ناتج الانشطار

(تم التحويل من Fission product yield)
المقالة الرئيسية: ناتج انشطار نووي
نواتج الانشطار المعمرة
النيوكليد t1⁄2 العائد Q[a 1] βγ
(Ma) (%)[a 2] (keV)
99Tc 0.211 6.1385 294 β
126Sn 0.230 0.1084 4050[a 3] βγ
79Se 0.327 0.0447 151 β
135Cs 1.33  6.9110[a 4] 269 β
93Zr 1.53  5.4575 91 βγ
107Pd 6.5   1.2499 33 β
129I 15.7   0.8410 194 βγ
  1. ^ Decay energy is split among β, neutrino, and γ if any.
  2. ^ Per 65 thermal neutron fissions of 235U and 35 of 239Pu.
  3. ^ Has decay energy 380 keV, but its decay product 126Sb has decay energy 3.67 MeV.
  4. ^ Lower in thermal reactors because 135Xe, its predecessor, readily absorbs neutrons.
Medium-lived
fission products
Prop:
Unit:		 t½
a		 Yield
%		 Q *
keV		 βγ
*
155Eu 4.76 .0803 252 βγ
85Kr 10.76 .2180 687 βγ
113mCd 14.1 .0008 316 β
90Sr 28.9 4.505 2826 β
137Cs 30.23 6.337 1176 βγ
121mSn 43.9 .00005 390 βγ
151Sm 96.6 .5314 77 β

Nuclear fission splits a heavy nucleus such as uranium or plutonium into two lighter nuclei, which are called fission products. Yield refers to the fraction of a fission product produced per fission.

Yield can be broken down by:

  1. Individual isotope
  2. Chemical element spanning several isotopes of different mass number but same atomic number.
  3. Nuclei of a given mass number regardless of atomic number. Known as "chain yield" because it represents a decay chain of beta decay.

Isotope and element yields will change as the fission products undergo beta decay, while chain yields do not change after completion of neutron emission by a few neutron-rich initial fission products (delayed neutrons), 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%).

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منحنى الكتلة مقابل العائد

 
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 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,[1] as nuclei closer to magic numbers are more stable.[2]

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).

 
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 100,1,2,3 years after fission, not considering later neutron capture, fraction of 100% not 200%. Beta decay Kr-85→Rb, Sr-90→Zr, Ru-106→Pd, Sb-125→Te, Cs-137→Ba, Ce-144→Nd, Sm-151→Eu, Eu-155→Gd visible.

Because of the stability of nuclei with even numbers of protons and/or neutrons the curve of yield against element is not a smooth curve. It tends to alternate.

In general, the higher the energy of the state that undergoes nuclear fission, the more likely a symmetric fission is, hence as the neutron energy increases and/or the energy of the fissile atom increases, the valley between the two peaks becomes more shallow; for instance, the curve of yield against mass for Pu-239 has a more shallow valley than that observed for U-235, when the neutrons are thermal neutrons. The curves for the fission of the later actinides tend to make even more shallow valleys. In extreme cases such as 259Fm, only one peak is seen.

Yield is usually expressed relative to number of fissioning nuclei, not the number of fission product nuclei, that is, yields should sum to 200%.

The table in the next section ("Ordered by yield") gives yields for notable radioactive (with half-lives greater than one year, plus iodine-131) fission products, and (the few most absorptive) neutron poison fission products, from thermal neutron fission of U-235 (typical of nuclear power reactors), computed from [1][dead link].

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

t½ 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.:

  • 135Xe capturing a neutron and becoming nearly stable 136Xe, rather than decaying to 135Cs which is radioactive with a half-life of 2.3 million years
  • Nonradioactive 133Cs capturing a neutron and becoming 134Cs, which is radioactive with a half-life of 2 years
  • Many of the fission products with mass 147 or greater such as 147Pm, 149Sm, 151Sm, and 155Eu 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


نواتج الانشطار من U-235

Yield Element Isotope Halflife Comment
6.7896% Caesium 133Cs → 134Cs &0000000000000002000000 2.065 y Neutron capture (29 barns) slowly converts stable 133Cs to 134Cs, which itself is low-yield because beta decay stops at 134Xe; can be further converted (140 barns) to 135Cs.
6.3333% Iodine, xenon 135I → 135Xe &0000000000000000000600 6.57 h Most important neutron poison; neutron capture converts 10–50% of 135Xe to 136Xe; remainder decays (9.14h) to 135Cs (2.3 My).
6.2956% Zirconium 93Zr &0000000001530000000000 1.53 My Long-lived fission product also produced by neutron activation in zircalloy cladding.
6.1% Molybdenum 99Mo &0000000000000000003000 65.94 h Its daughter nuclide 99mTc is important in medical diagnosing.
6.0899% Caesium 137Cs &0000000000000030000000 30.17 y Source of most of the decay heat from years to decades after irradiation, together with 90 Sr.
6.0507% Technetium 99Tc &0000000000211000000000 211 ky Candidate for disposal by nuclear transmutation.
5.7518% Strontium 90Sr &0000000000000029000000 28.9 y Source of much of the decay heat together with 137 Cs on the timespan of years to decades after irradiation. Formerly used in radioisotope thermoelectric generators.
2.8336% Iodine 131I &0000000000000000008000 8.02 d Reason for the use of potassium iodide tablets after nuclear accidents or nuclear bomb explosions.
2.2713% Promethium 147Pm &0000000000000002600000 2.62 y beta decays to very long lived Samarium-147 (half life>age of the universe); has seen some use in radioisotope thermoelectric generators
1.0888% Samarium 149Sm &0000000100000000000000 Observationally stable 2nd most significant neutron poison.
0.9%[3] Iodine 129I &0000000015700000000000 15.7 My Long-lived fission product. Candidate for disposal by nuclear transmutation.
0.4203% Samarium 151Sm &0000000000000090000000 90 y Neutron poison; most will be converted to stable 152Sm.
0.3912% Ruthenium 106Ru &0000000000000001000000 373.6 d ruthenium tetroxide is volatile and chemically aggressive; daughter nuclide 106 Rh decays quickly to stable 106 Pd
0.2717% Krypton 85Kr &0000000000000011000000 10.78 y noble gas; has some uses in industry to detect fine cracks in materials via autoradiography
0.1629% Palladium 107Pd &0000000006500000000000 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 79Se &0000000000327000000000 327 ky
0.0330% Europium, gadolinium 155Eu → 155Gd &0000000000000005000000 4.76 y Both neutron poisons, most will be destroyed while fuel still in use.
0.0297% Antimony 125Sb &0000000000000002799999 2.76 y
0.0236% Tin 126Sn &0000000000230000000000 230 ky
0.0065% Gadolinium 157Gd &0000000100000000000000 stable Neutron poison.
0.0003% Cadmium 113mCd &0000000000000014000000 14.1 y Neutron poison, most will be destroyed while fuel still in use.
 
Yields at 100,1,2,3 years after fission, probably of Pu-239 not U-235 because left hump is shifted right, not considering later neutron capture, fraction of 100% not 200%. Beta decay Kr-85→Rb, Sr-90→Zr, Ru-106→Pd, Sb-125→Te, Cs-137→Ba, Ce-144→Nd, Sm-151→Eu, Eu-155→Gd visible.

العوائد التراكمية للانشطار

Cumulative fission yields give the amounts of nuclides produced either directly in the fission or by decay of other nuclides.

Cumulative fission yields per fission for U-235 (%)[4]
الناتج Thermal fission yield Fast fission yield 14-MeV fission yield
11H 0.00171 ± 0.00018 0.00269 ± 0.00044 0.00264 ± 0.00045
21H 0.00084 ± 0.00015 0.00082 ± 0.00012 0.00081 ± 0.00012
31H 0.0108 ± 0.0004 0.0108 ± 0.0004 0.0174 ± 0.0036
32He 0.0108 ± 0.0004 0.0108 ± 0.0004 0.0174 ± 0.0036
42He 0.1702 ± 0.0049 0.17 ± 0.0049 0.1667 ± 0.0088
8535Br 1.304 ± 0.012 1.309 ± 0.043 1.64 ± 0.31
8236Kr 0.000285 ± 0.000076 0.00044 ± 0.00016 0.038 ± 0.012
8536Kr 0.286 ± 0.021 0.286 ± 0.026 0.47 ± 0.1
85m36Kr 1.303 ± 0.012 1.307 ± 0.043 1.65 ± 0.31
9038Sr 5.73 ± 0.13 5.22 ± 0.18 4.41 ± 0.18
9540Zr 6.502 ± 0.072 6.349 ± 0.083 5.07 ± 0.19
9441Nb 0.00000042 ± 0.00000011 2.90±0.770 × 10−8 0.00004 ± 0.000015
9541Nb 6.498 ± 0.072 6.345 ± 0.083 5.07 ± 0.19
95m41Nb 0.0702 ± 0.0067 0.0686 ± 0.0071 0.0548 ± 0.0072
9242Mo 0 ± 0 0 ± 0 0 ± 0
9442Mo 8.70 × 10−10 ± 3.20 × 10−10 0 ± 0 6.20 × 10−8 ± 2.50 × 10−8
9642Mo 0.00042 ± 0.00015 0.000069 ± 0.000025 0.0033 ± 0.0015
9942Mo 6.132 ± 0.092 5.8 ± 0.13 5.02 ± 0.13
9943Tc 6.132 ± 0.092 5.8 ± 0.13 5.02 ± 0.13
10344Ru 3.103 ± 0.084 3.248 ± 0.042 3.14 ± 0.11
10644Ru 0.41 ± 0.011 0.469 ± 0.036 2.15 ± 0.59
10645Rh 0.41 ± 0.011 0.469 ± 0.036 2.15 ± 0.59
121m50Sn 0.00106 ± 0.00011 0.0039 ± 0.00091 0.142 ± 0.023
12251Sb 0.000000366 ± 0.000000098 0.0000004 ± 0.00000014 0.00193 ± 0.00068
12451Sb 0.000089 ± 0.000021 0.000112 ± 0.000034 0.027 ± 0.01
12551Sb 0.026 ± 0.0014 0.067 ± 0.011 1.42 ± 0.42
13252Te 4.276 ± 0.043 4.639 ± 0.065 3.85 ± 0.16
12953I 0.706 ± 0.032 1.03 ± 0.26 1.59 ± 0.18
13153I 2.878 ± 0.032 3.365 ± 0.054 4.11 ± 0.14
13353I 6.59 ± 0.11 6.61 ± 0.13 5.42 ± 0.4
13553I 6.39 ± 0.22 6.01 ± 0.18 4.8 ± 1.4
12854Xe 0 ± 0 0 ± 0 0.00108 ± 0.00048
13054Xe 0.000038 ± 0.0000098 0.000152 ± 0.000055 0.038 ± 0.014
131m54Xe 0.0313 ± 0.003 0.0365 ± 0.0031 0.047 ± 0.0049
13354Xe 6.6 ± 0.11 6.61 ± 0.13 5.57 ± 0.41
133m54Xe 0.189 ± 0.015 0.19 ± 0.015 0.281 ± 0.049
13554Xe 6.61 ± 0.22 6.32 ± 0.18 6.4 ± 1.8
135m54Xe 1.22 ± 0.12 1.23 ± 0.13 2.17 ± 0.66
13455Cs 0.0000121 ± 0.0000032 0.0000279 ± 0.0000073 0.0132 ± 0.0035
13755Cs 6.221 ± 0.069 5.889 ± 0.096 5.6 ± 1.3
14056Ba 6.314 ± 0.095 5.959 ± 0.048 4.474 ± 0.081
14057La 6.315 ± 0.095 5.96 ± 0.048 4.508 ± 0.081
14158Ce 5.86 ± 0.15 5.795 ± 0.081 4.44 ± 0.2
14458Ce 5.474 ± 0.055 5.094 ± 0.076 3.154 ± 0.038
14459Pr 5.474 ± 0.055 5.094 ± 0.076 3.155 ± 0.038
14260Nd 6.30 × 10−9 ± 1.70 × 10−9 1.70 × 10−9 ± 4.80 × 10−10 0.0000137 ± 0.0000049
14460Nd 5.475 ± 0.055 5.094 ± 0.076 3.155 ± 0.038
14760Nd 2.232 ± 0.04 2.148 ± 0.028 1.657 ± 0.045
14761Pm 2.232 ± 0.04 2.148 ± 0.028 1.657 ± 0.045
14861Pm 5.00 × 10−8 ± 1.70 × 10−8 7.40 × 10−9 ± 2.50 × 10−9 0.0000013 ± 0.00000042
148m61Pm 0.000000104 ± 0.000000039 1.78 × 10−8 ± 6.60 × 10−9 0.0000048 ± 0.0000018
14961Pm 1.053 ± 0.021 1.064 ± 0.03 0.557 ± 0.09
15161Pm 0.4204 ± 0.0071 0.431 ± 0.015 0.388 ± 0.061
14862Sm 0.000000149 ± 0.000000041 2.43 × 10−8 ± 6.80 × 10−9 0.0000058 ± 0.0000018
15062Sm 0.000061 ± 0.000022 0.0000201 ± 0.0000077 0.00045 ± 0.00018
15162Sm 0.4204 ± 0.0071 0.431 ± 0.015 0.388 ± 0.061
15362Sm 0.1477 ± 0.0071 0.1512 ± 0.0097 0.23 ± 0.015
15163Eu 0.4204 ± 0.0071 0.431 ± 0.015 0.388 ± 0.061
15263Eu 3.24 × 10−10 ± 8.50 × 10−11 0 ± 0 3.30 × 10−8 ± 1.10 × 10−8
15463Eu 0.000000195 ± 0.000000064 4.00 × 10−8 ± 1.10 × 10−8 0.0000033 ± 0.0000011
15563Eu 0.0308 ± 0.0013 0.044 ± 0.01 0.088 ± 0.014
Cumulative fission yield per fission for Pu-239 (%)[4]
Product Thermal fission yield Fast fission yield 14-MeV fission yield
11H 0.00408 ± 0.00041 0.00346 ± 0.00057 -
21H 0.00135 ± 0.00019 0.00106 ± 0.00016 -
31H 0.0142 ± 0.0007 0.0142 ± 0.0007 -
32He 0.0142 ± 0.0007 0.0142 ± 0.0007 -
42He 0.2192 ± 0.009 0.219 ± 0.009 -
8535Br 0.574 ± 0.026 0.617 ± 0.049 -
8236Kr 0.00175 ± 0.0006 0.00055 ± 0.0002 -
8536Kr 0.136 ± 0.014 0.138 ± 0.017 -
85m36Kr 0.576 ± 0.026 0.617 ± 0.049 -
9038Sr 2.013 ± 0.054 2.031 ± 0.057 -
9540Zr 4.949 ± 0.099 4.682 ± 0.098 -
9441Nb 0.0000168 ± 0.0000045 0.00000255 ± 0.00000069 -
9541Nb 4.946 ± 0.099 4.68 ± 0.098 -
95m41Nb 0.0535 ± 0.0066 0.0506 ± 0.0062 -
9242Mo 0 ± 0 0 ± 0 -
9442Mo 3.60 × 10−8 ± 1.30 × 10−8 4.80 × 10−9 ± 1.70 × 10−9 -
9642Mo 0.0051 ± 0.0018 0.0017 ± 0.00062 -
9942Mo 6.185 ± 0.056 5.82 ± 0.13 -
9943Tc 6.184 ± 0.056 5.82 ± 0.13 -
10344Ru 6.948 ± 0.083 6.59 ± 0.16 -
10644Ru 4.188 ± 0.092 4.13 ± 0.24 -
10645Rh 4.188 ± 0.092 4.13 ± 0.24 -
121m50Sn 0.0052 ± 0.0011 0.0053 ± 0.0012 -
12251Sb 0.000024 ± 0.0000063 0.0000153 ± 0.000005 -
12451Sb 0.00228 ± 0.00049 0.00154 ± 0.00043 -
12551Sb 0.117 ± 0.015 0.138 ± 0.022 -
13252Te 5.095 ± 0.094 4.92 ± 0.32 -
12953I 1.407 ± 0.086 1.31 ± 0.13 -
13153I 3.724 ± 0.078 4.09 ± 0.12 -
13353I 6.97 ± 0.13 6.99 ± 0.33 -
13553I 6.33 ± 0.23 6.24 ± 0.22 -
12854Xe 0.00000234 ± 0.00000085 0.0000025 ± 0.0000012 -
13054Xe 0.00166 ± 0.00056 0.00231 ± 0.00085 -
131m54Xe 0.0405 ± 0.004 0.0444 ± 0.0044 -
13354Xe 6.99 ± 0.13 7.03 ± 0.33 -
133m54Xe 0.216 ± 0.016 0.223 ± 0.021 -
13554Xe 7.36 ± 0.24 7.5 ± 0.23 -
135m54Xe 1.78 ± 0.21 1.97 ± 0.25 -
13455Cs 0.00067 ± 0.00018 0.00115 ± 0.0003 -
13755Cs 6.588 ± 0.08 6.35 ± 0.12 -
14056Ba 5.322 ± 0.059 5.303 ± 0.074 -
14057La 5.333 ± 0.059 5.324 ± 0.075 -
14158Ce 5.205 ± 0.073 5.01 ± 0.16 -
14458Ce 3.755 ± 0.03 3.504 ± 0.053 -
14459Pr 3.756 ± 0.03 3.505 ± 0.053 -
14260Nd 0.00000145 ± 0.0000004 0.00000251 ± 0.00000072 -
14460Nd 3.756 ± 0.03 3.505 ± 0.053 -
14760Nd 2.044 ± 0.039 1.929 ± 0.046 -
14761Pm 2.044 ± 0.039 1.929 ± 0.046 -
14861Pm 0.0000056 ± 0.0000019 0.000012 ± 0.000004 -
148m61Pm 0.0000118 ± 0.0000044 0.000029 ± 0.000011 -
14961Pm 1.263 ± 0.032 1.275 ± 0.056 -
15161Pm 0.776 ± 0.018 0.796 ± 0.037 -
14862Sm 0.0000168 ± 0.0000046 0.000039 ± 0.000011 -
15062Sm 0.00227 ± 0.00078 0.0051 ± 0.0019 -
15162Sm 0.776 ± 0.018 0.797 ± 0.037 -
15362Sm 0.38 ± 0.03 0.4 ± 0.18 -
15163Eu 0.776 ± 0.018 0.797 ± 0.037 -
15263Eu 0.000000195 ± 0.00000005 0.00000048 ± 0.00000014 -
15463Eu 0.000049 ± 0.000012 0.000127 ± 0.000043 -
15563Eu 0.174 ± 0.03 0.171 ± 0.054 -
JEFF-3.1

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.

 
Yields at 100,1,2,3 years after fission, probably of Pu-239 not U-235 because left hump is shifted right, not considering later neutron capture, fraction of 100% not 200%. Beta decay Kr-85→Rb, Sr-90→Zr, Ru-106→Pd, Sb-125→Te, Cs-137→Ba, Ce-144→Nd, Sm-151→Eu, Eu-155→Gd visible.


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مرتبة حسب عدد الكتلة

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 (*), while decays with a half life longer than a hundred million years are marked with two asterisks (**).

Yield Isotope
0.0508% selenium-79→* bromine-79
0.2717% krypton-85→ rubidium-85
5.7518% strontium-90 → yttrium-90→ zirconium-90
6.2956% zirconium-93 →* niobium-93
6.0507% technetium-99→* ruthenium-99
0.3912% ruthenium-106→ rhodium-106→ palladium-106
0.1629% palladium-107→* silver-107
0.0003% cadmium-113m→ cadmium-113→** indium-113
0.0297% antimony-125→ tellurium-125m→ tellurium-125
0.0236% tin-126 →* antimony-126→ tellurium-126
0.9% iodine-129→* xenon-129
2.8336% iodine-131→ xenon-131
6.7896% caesium-133 → caesium-134→ barium-134
6.3333% iodine-135 → xenon-135 → caesium-135→* barium-135
6.3333% iodine-135 → xenon-135 → xenon-136 (essentially stable)→** barium-136
6.0899% caesium-137→ barium-137
2.2713% promethium-147→ samarium-147→* neodymium-143
1.0888% samarium-149
0.4203% samarium-151
0.0330% europium-155 → gadolinium-155
0.0065% gadolinium-157

أعمار النصف وأنماط الاضمحلال وكسور التفرع

Half-lives and decay branching fractions for fission products[5]
Nuclide Half-life Decay mode Branching fraction Source Notes
8535Br 2.9 ± 0.06 m β− 1.0 [6] [أ]
8536Kr 10.752 ± 0.023 y β− 1.0 [7]
85m36Kr 4.48 ± 0.008 h IT 0.214 ± 0.005 [6]
β− 0.786 ± 0.005
9038Sr 28.8 ± 0.07 y β− 1.0 [8]
9540Zr 64.032 ± 0.006 d β− 1.0 [8]
9441Nb (7.3 ± 0.9) × 106 d β− 1.0 [9]
95m41Nb 3.61 ± 0.03 d β− 0.025 ± 0.001 [8] [ب]
IT 0.975 ± 0.001
9541Nb 34.985 ± 0.012 d β− 1.0 [9]
9943Tc (2.111 ± 0.012) × 105 y β− 1.0 [6]
10344Ru 39.247 ± 0.013 d β− 1.0 [9]
10644Ru 1.018 ± 0.005 y β− 1.0 [9]
10645Rh 30.1 ± 0.3 s β− 1.0 [9]
121m50Sn 55 ± 5 y β− 0.224 ± 0.02 [6]
IT 0.776 ± 0.02
12251Sb 2.7238 ± 0.0002 d EC 0.0241 ± 0.0012 [6]
β− 0.9759 ± 0.0012
12451Sb 60.2 ± 0.03 d β− 1.0 [6]
12551Sb 2.7584 ± 0.0006 y β− 1.0 [9]
12953I (5.89 ± 0.23) × 109 d β− 1.0 [9]
13153I 8.0233 ± 0.0019 d β− 1.0 [7]
13353I 20.87 ± 0.08 h β− 1.0 [8] [ت]
13553I 6.57 ± 0.02 h β− 1.0 [6]
131m54Xe 11.930 ± 0.016 d IT 1.0 [7]
13354Xe 5.243 ± 0.001 d β− 1.0 [6]
133m54Xe 2.19 ± 0.01 d IT 1.0 [6]
13554Xe 9.14 ± 0.02 h β− 1.0 [6]
135m54Xe 15.29 ± 0.05 m β− 0.003 ± 0.003 [6] [ث]
IT 0.997 ± 0.003
13455Cs 2.063 ± 0.003 y EC 0.000003 ± 0.000001 [9] [ج]
β− 0.999997 ± 0.000001
13755Cs 30.05 ± 0.08 y β− 1.0 [9]
14056Ba 12.753 ± 0.004 d β− 1.0 [7]
14057La 1.67850 ± 0.00017 d β− 1.0 [7]
14158Ce 32.508 ± 0.010 d β− 1.0 [8]
14458Ce 285.1 ± 0.6 d β− 1.0 [9]
14459Pr 17.28 ± 0.05 m β− 1.0 [6]
14760Nd 10.98 ± 0.01 d β− 1.0 [6]
14761Pm 2.6234 ± 0.0002 y β− 1.0 [6]
148m61Pm 41.29 ± 0.11 d IT 0.042 ± 0.007 [6]
β− 0.958 ± 0.007
14861Pm 5.368 ± 0.002 d β− 1.0 [6]
14961Pm 2.2117 ± 0.0021 d β− 1.0 [6]
15161Pm 1.1833 ± 0.0017 d β− 1.0 [6]
15162Sm 90 ± 6 y β− 1.0 [6]
15362Sm 1.938 ± 0.010 d β− 1.0 [9]
15263Eu (4.941 ± 0.007) × 103 d β− 0.279 ± 0.003 [9] [ح]
EC 0.721 ± 0.003
15463Eu (3.1381 ± 0.0014) × 103 d EC 0.00018 ± 0.00013 [9] [ح]
β− 0.99982 ± 0.00013
15563Eu 4.753 ± 0.016 y β− 1.0 [9]
  1. ^ β−  decay branches of 0.9982 ± 0.0002 to Kr-85m and 0.0018 ± 0.0002 to Kr-85.
  2. ^ ENSDF branching fractions: 0.944 ± 0.007 for IT and 0.056 ± 0.007 for β− .
  3. ^ β−  decay branch of 0.0288 ± 0.0002 to Xe-133m.
  4. ^ Branching fractions were averaged from ENSDF database.
  5. ^ Branching fractions were adopted from ENSDF database.
  6. ^ أ ب Branching fractions were adopted from LNHB data.


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مرتبة حسب مقاطع الامتصاص الحراري للنيوترونات

Barns Yield النظير t½ تعليق
&&&&&&&&02650000.&&&&&02٬650٬000 6.3333% 135I → 135Xe &0000000000000000000600 6.57 h Most important neutron poison; neutron capture rapidly converts 135Xe to 136Xe; remainder decays (9.14 h) to 135Cs (2.3 My).
&&&&&&&&&0254000.&&&&&0254٬000 0.0065% 157Gd ∞ Neutron poison, but low yield.
&&&&&&&&&&040140.&&&&&040٬140 1.0888% 149Sm ∞ 2nd most important neutron poison.
&&&&&&&&&&020600.&&&&&020٬600 0.0003% 113mCd &0000000000000014000000 14.1 y Most will be destroyed by neutron capture.
&&&&&&&&&&015200.&&&&&015٬200 0.4203% 151Sm &0000000000000090000000 90 y Most will be destroyed by neutron capture.
&&&&&&&&&&&03950.&&&&&03٬950
60,900		 0.0330% 155Eu → 155Gd &0000000000000005000000 4.76 y Both neutron poisons.
&&&&&&&&&&&&&096.&&&&&096 2.2713% 147Pm &0000000000000002600000 2.62 y Suitable for radioisotope thermoelectric generators with annual or semi-annual refueling.
&&&&&&&&&&&&&080.&&&&&080 2.8336% 131I &0000000000000000008000 8.02 d
&&&&&&&&&&&&&029.&&&&&029
140		 6.7896% 133Cs → 134Cs ∞
2.065 y		 Neutron capture converts a few percent of nonradioactive 133Cs to 134Cs, which has very low direct yield because beta decay stops at 134Xe; further capture will add to long-lived 135Cs.
&&&&&&&&&&&&&020.&&&&&020 6.0507% 99Tc &0000000000211000000000 211 ky Candidate for disposal by nuclear transmutation.
&&&&&&&&&&&&&018.&&&&&018 0.6576% 129I &0000000015700000000000 15.7 My Candidate for disposal by nuclear transmutation.
&&&&&&&&&&&&&&02.7000002٫7 6.2956% 93Zr &0000000001530000000000 1.53 My Transmutation impractical.
&&&&&&&&&&&&&&01.8000001٫8 0.1629% 107Pd &0000000006500000000000 6.5 My
&&&&&&&&&&&&&&01.6600001٫66 0.2717% 85Kr &0000000000000011000000 10.78 y
&&&&&&&&&&&&&&00.9000000٫90 5.7518% 90Sr &0000000000000029000000 28.9 y
&&&&&&&&&&&&&&00.1500000٫15 0.3912% 106Ru &0000000000000001000000 373.6 d
&&&&&&&&&&&&&&00.1100000٫11 6.0899% 137Cs &0000000000000030000000 30.17 y
0.0297% 125Sb &0000000000000002700000 2.76 y
0.0236% 126Sn &0000000000230000000000 230 ky
0.0508% 79Se &0000000000327000000000 327 ky

المراجع

  1. ^ "fissionyield". Archived from the original on 2007-05-28. Retrieved 2007-06-10.
  2. ^ Möller, P; Madland, DG; Sierk, AJ; Iwamoto, A (15 February 2001). "Nuclear fission modes and fragment mass asymmetries in a five-dimensional deformation space". Nature. 409 (6822): 785–790. Bibcode:2001Natur.409..785M. doi:10.1038/35057204. PMID 11236985. S2CID 9754793.
  3. ^ 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.
  4. ^ أ ب "Cumulative Fission Yields". www-nds.iaea.org. IAEA. Retrieved 11 November 2016.
  5. ^ "Half-lives and decay branching fractions for activation products". www-nds.iaea.org. IAEA. Retrieved 11 November 2016.
  6. ^ أ ب ت ث ج ح خ د ذ ر ز س ش ص ض ط ظ ع غ Evaluated Nuclear Structure Data File, http://www-nds.iaea.org/ensdf/, 26 January 2006.
  7. ^ أ ب ت ث ج 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.
  8. ^ أ ب ت ث ج Laboratoire National Henri Becquerel, Recommended Data, http://www.nucleide.org/DDEP_WG/DDEPdata.htm, 16 January 2006.
  9. ^ أ ب ت ث ج ح خ د ذ ر ز س ش ص 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.

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