Table of nuclides

This is a table of all nuclides with masses between 228 and 260, and atomic numbers between 90 (thorium) and 100 (fermium). The word "nuclide" refers to a nucleus with a specified number of protons and neutrons. This is to be contrasted with the word "isotope", which refers to a nucleus of a specific element that has a specified number of neutrons, and the word "element" which refers to a nucleus with a specified bumber of protons but an unspecified number of neutrons. The word "isotope" is often erroneously used in place of "nuclide", but these are in fact slightly different concepts. If you speak a specific nucleus without context, such as "Plutonium 239", it would properly be called a nuclide. However, if it is already established that you are talking about plutonium in particular, then "Plutonium 239" can be called an isotope. You can also say something like "Plutonium 239 is an isotope of plutonium" even without previous context. In other words, if you are speaking of a specific element, the word "isotope" is to be used, and if you are merely speaking of nuclei in general, the word "nuclide" is to be used instead.

Ok, enough on definitions. What does this table show? Each cell contains a variety of data for a specific nuclide. In the center is the atomic symbol for the element that the nuclide is an isotope of, as well as the mass of the nuclide in atomic mass units. In the lower left corner is the half life of the element, which ranges from as little as four microseconds to as much as 14 billion years. This half life also determines the background color, starting at purple for very short lived nuclides and going around the rainbow through blue, green, yellow, and finally to red as the half lives grow progressively longer. In the lower right corner is the decay mode for that nuclide. If it decays in significant proportion by multiple modes, all relevant modes are shown with percentages to indicate the branching ratio, if that data is available. In the two upper corners is neutronics data, which concerns the interaction of the nuclide with thermal neutrons.

I represent the neutronics data in two different formats. I call the first one "absolute format" and the second one "relative format", but these are really just random names that I came up with to distinguish the two. These names do not have any greater meaning than that. To see the data presented in each format, simply select the corresponding radio button and the table will automatically adjust itself.

Absolute format

In the upper left corner is the number of prompt neutrons released per fission event, in neutrons, and below it is the number of delayed neutrons released per fission event, in millineutrons (thousandths of a neutron). These numbers are fractional because it is a statistical average. Any given fission event will always release a whole number of prompt and delayed neutrons, although the vast majority of fission events do not release any delayed neutrons at all.

In the upper right corner is the neutron capture cross-section, and below it is the fission cross-section, both in barns.

Relative format

In the upper left corner is the number of total neutrons (prompt and delayed) released per neutron absorption event, in neutrons, and below it is the percentage of released neutrons that are delayed neutrons.

In the upper right corner is the neutron absorption cross-section, in barns, and below it is the percentage chance that the neutron absorption event will cause the nucleus to fission.




Fm-228
Fm-229
Fm-230
Fm-231
Fm-232
Fm-233
Fm-234
Fm-235
Fm-236
Fm-237
Fm-238
Fm-239
Fm-240
Fm-241
730 μs
SF
Fm-242
4 μs
SF
Fm-243
231 ms
9% SF
91% α
Fm-244
3.12 ms
SF
Fm-245
5.5 s
12% β+
88% α
Fm-246
1.54 s
7% β+
93% α
Fm-247
31 s
36% β+
64% α
Fm-248
35.1 s
7% β+
93% α
Fm-249
1.6 m
16% α
84% β+
Fm-250
30.4 m
10% EC
90% α
Fm-251
5.30 h
2% α
98% β+
Fm-252
25.39 h
α
Fm-253
3.00 d
12% α
88% EC
Fm-254
3.240 h
α
4 n
2.733 mn
270.3 b
3366 b
Fm-255
20.07 h
α
Fm-256
157.6 m
8% α
92% SF
Fm-257
100.5 d
α
Fm-258
370 μs
SF
Fm-259
1.5 s
SF
Fm-260
4 ms
SF
Es-228
Es-229
Es-230
Es-231
Es-232
Es-233
Es-234
Es-235
Es-236
Es-237
Es-238
Es-239
Es-240
6 s
30% β+
70% α
Es-241
4.3 s
β+
α
Es-242
17.8 s
43% β+
57% α
Es-243
23 s
39% α
61% β+
Es-244
37 s
5% α
95% β+
Es-245
1.11 m
49% α
51% β+
Es-246
7.7 m
10% α
90% β+
Es-247
4.55 m
7% α
93%β+
Es-248
27 m
β+
Es-249
102.2 m
1% α
99% β+
Es-250
8.6 h
3% α
97% β+
3.915 n
1.938 mn
200.1 b
43.11 b
Es-251
33 h
EC
4.141 n
2.818 mn
201.3 b
2012 b
Es-252
471.7 d
24% EC
76% α
3.881 n
4.107 mn
188.4 b
2.511 b
Es-253
20.47 d
α
4.077 n
5.999 mn
28.33 b
2133 b
Es-254
275.7 d
α
3.866 n
8.760 mn
55.43 b
0.503 b
Es-255
39.8 d
8% α
92% β-
Es-256
25.4 m
β-
Es-257
7.7 d
α
β-
Es-258
Es-259
Es-260
Cf-228
Cf-229
Cf-230
Cf-231
Cf-232
Cf-233
Cf-234
Cf-235
Cf-236
Cf-237
0.8 s
30% SF
70% α
Cf-238
21.1 ms
SF
Cf-239
28 s
35% β+
65% α
Cf-240
40.3 s
1% SF
99% α
Cf-241
2.35 m
15% α
85% β+
Cf-242
3.49 m
39% β+
61% α
Cf-243
10.8 m
14% α
86% β+
Cf-244
19.5 m
25% EC
75% α
Cf-245
45.0 m
35% α
65% β+
3.771 n
0.952 mn
1703 b
1402 b
Cf-246
35.7 h
α
Cf-247
3.11 h
EC
3.708 n
1.994 mn
1699 b
700.4 b
Cf-248
333.5 d
α
4.06 n
2.800 mn
491.2 b
1620 b
Cf-249
351 y
α
3.63 n
4.060 mn
1974 b
105.0 b
Cf-250
13.08 y
α
4.1 n
5.900 mn
2839 b
4895 b
Cf-251
900 y
α
3.884 n
8.300 mn
20.62 b
32.96 b
Cf-252
2.645 y
3% SF
97% α
3.839 n
13.20 mn
19.95 b
1303 b
Cf-253
17.81 d
β-
3.831 n
19.39 mn
4.510 b
2.001 b
Cf-254
60.5 d
β-
Cf-255
85 m
β-
Cf-256
12.3 m
SF
Cf-257
Cf-258
Cf-259
Cf-260
Bk-228
Bk-229
Bk-230
0.46 s
α
Bk-231
Bk-232
Bk-233
20 s
α
Bk-234
20 s
α
Bk-235
Bk-236
20 s
β+
Bk-237
Bk-238
2.4 m
β+
Bk-239
100 s
β+
Bk-240
4.8 m
β+
Bk-241
4.6 m
β+
Bk-242
7.0 m
β+
Bk-243
4.5 h
β+
Bk-244
4.35 h
β+
3.575 n
2.052 mn
1001 b
2.907 b
Bk-245
4.94 d
EC
3.668 n
2.978 mn
699.5 b
1807 b
Bk-246
1.80 d
β+
3.503 n
4.198 mn
1001 b
3.706 b
Bk-247
1380 y
α
3.664 n
6.313 mn
859.1 b
2001 b
Bk-248
300 y
α
3.41 n
8.900 mn
1069 b
5.962 b
Bk-249
330 d
β-
3.559 n
13.00 mn
782.7 b
982.7 b
Bk-250
3.212 h
β-
Bk-251
55.6 m
β-
Bk-252
1.8 m
β-
Bk-253
10 m
β-
Bk-254
Bk-255
Bk-256
Bk-257
Bk-258
Bk-259
Bk-260
Cm-228
Cm-229
Cm-230
Cm-231
Cm-232
Cm-233
23 s
20% α
80% β+
Cm-234
52 s
28% α
72% β+
Cm-235
300 s
1% α
99% β+
Cm-236
6.8 m
18% α
82% β+
Cm-237
20 m
β+
Cm-238
2.2 h
6% α
94% EC
Cm-239
2.5 h
β+
3.285 n
1.020 mn
49.99 b
30.05 b
Cm-240
27 d
α
3.39 n
1.460 mn
199.9 b
999.5 b
Cm-241
32.8 d
1% α
99% EC
3.452 n
2.114 mn
19.06 b
4.646 b
Cm-242
162.8 d
α
3.429 n
3.010 mn
129.0 b
591.1 b
Cm-243
29.1 y
α
3 n
4.451 mn
15.25 b
1.019 b
Cm-244
18.10 y
α
3.59 n
6.482 mn
324.4 b
1935 b
Cm-245
8500 y
α
2.98 n
9.160 mn
1.186 b
0.044 b
Cm-246
4760 y
α
3.79 n
13.40 mn
59.97 b
95.11 b
Cm-247
15.6 My
α
3.11 n
19.60 mn
2.879 b
0.337 b
Cm-248
348 ky
8% SF
92% α
3.32 n
28.80 mn
1.602 b
10.01 b
Cm-249
64.15 m
β-
3.356 n
44.04 mn
81.20 b
0.021 b
Cm-250
8300 y
20% α
80% SF
Cm-251
16.8 m
β-
Cm-252
Cm-253
Cm-254
Cm-255
Cm-256
Cm-257
Cm-258
Cm-259
Cm-260
Am-228
Am-229
1.8 s
α
Am-230
40 s
β+
Am-231
Am-232
1.31 m
3% α
97% β+
Am-233
3.2 m
5% α
95% β+
Am-234
2.32 m
β+
Am-235
10.3 m
β+
Am-236
3.6 m
β+
Am-237
73.6 m
β+
Am-238
98 m
β+
Am-239
11.9 h
EC
3.183 n
3.154 mn
280.6 b
1500 b
Am-240
50.8 h
β+
3.111 n
4.900 mn
691.4 b
3.191 b
Am-241
432.6 y
α
3.264 n
6.659 mn
353.5 b
2569 b
Am-242
16.02 h
17% EC
83% β-
3.187 n
8.500 mn
80.83 b
0.083 b
Am-243
7350 y
α
3.138 n
13.80 mn
999.8 b
2294 b
Am-244
10.01 h
β-
Am-245
2.05 h
β-
Am-246
39 m
β-
Am-247
23 m
β-
Am-248
Am-249
Am-250
Am-251
Am-252
Am-253
Am-254
Am-255
Am-256
Am-257
Am-258
Am-259
Am-260
Pu-228
1.1 s
α
Pu-229
91 s
50% β+
50% α
Pu-230
1.70 m
25% β+
75% α
Pu-231
8.6 m
13% α
87% β+
Pu-232
33.7 m
11% α
89% EC
Pu-233
20.9 m
β+
Pu-234
8.8 h
6% α
94% EC
Pu-235
25.3 m
β+
2.906 n
2.248 mn
27.61 b
139.4 b
Pu-236
2.858 y
α
2.863 n
2.000 mn
200.1 b
2302 b
Pu-237
45.2 d
EC
2.906 n
4.710 mn
386.8 b
16.67 b
Pu-238
87.7 y
α
2.872 n
6.220 mn
310.1 b
790.5 b
Pu-239
24.11 ky
α
2.825 n
9.110 mn
297.2 b
0.038 b
Pu-240
6561 y
α
2.931 n
16.00 mn
373.7 b
1060 b
Pu-241
14.29 y
β-
2.878 n
15.30 mn
20.09 b
0.002 b
Pu-242
375 ky
α
Pu-243
4.956 h
β-
2.79 n
30.00 mn
1.706 b
0.002 b
Pu-244
80.1 My
α
Pu-245
10.5 h
β-
2.58 n
98.20 mn
80.07 b
0.003 b
Pu-246
10.84 d
β-
Pu-247
2.27 d
β-
Pu-248
Pu-249
Pu-250
Pu-251
Pu-252
Pu-253
Pu-254
Pu-255
Pu-256
Pu-257
Pu-258
Pu-259
Pu-260
Np-228
61.4 s
41% α
59% β+
Np-229
4.0 m
49% β+
51% α
Np-230
4.6 m
3% α
97% β+
Np-231
48.8 m
2% α
98% β+
Np-232
14.7 m
β+
Np-233
36.2 m
β+
2.632 n
3.350 mn
110.2 b
2001 b
Np-234
4.4 d
β+
2.632 n
4.850 mn
157.2 b
53.78 b
Np-235
396.1 d
EC
2.4 n
7.040 mn
129.2 b
2863 b
Np-236
154 ky
13% β-
87% EC
2.615 n
12.00 mn
175.1 b
0.020 b
Np-237
2.144 My
α
2.47 n
14.94 mn
464.0 b
2226 b
Np-238
2.117 d
β-
2.699 n
21.86 mn
45.03 b
0.028 b
Np-239
2.356 d
β-
Np-240
61.9 m
β-
Np-241
13.9 m
β-
Np-242
2.2 m
β-
Np-243
1.85 m
β-
Np-244
2.29 m
β-
Np-245
Np-246
Np-247
Np-248
Np-249
Np-250
Np-251
Np-252
Np-253
Np-254
Np-255
Np-256
Np-257
Np-258
Np-259
Np-260
U-228
9.1 m
3% EC
97% α
U-229
57.8 m
20% α
80% β+
2.356 n
2.397 mn
200.0 b
25.01 b
U-230
20.32 d
α
2.442 n
3.457 mn
22.72 b
267.2 b
U-231
4.2 d
EC
3.123 n
5.030 mn
73.16 b
74.83 b
U-232
68.9 y
α
2.478 n
6.700 mn
46.74 b
529.7 b
U-233
159.2 ky
α
2.354 n
10.53 mn
98.39 b
0.066 b
U-234
245.5 ky
α
2.42 n
15.85 mn
97.83 b
571.4 b
U-235
703.8 My
α
2.361 n
22.50 mn
5.138 b
0.000 b
U-236
23.42 My
α
2.359 n
32.84 mn
441.8 b
1.674 b
U-237
6.752 d
β-
2.281 n
46.34 mn
2.690 b
0.000 b
U-238
4.468 Gy
α
U-239
23.45 m
β-
U-240
14.1 h
β-
U-241
40 m
β-
U-242
16.8 m
β-
U-243
U-244
U-245
U-246
U-247
U-248
U-249
U-250
U-251
U-252
U-253
U-254
U-255
U-256
U-257
U-258
U-259
U-260
Pa-228
22 h
2% α
98% β+
2.24 n
5.153 mn
408.5 b
1.071 b
Pa-229
1.5 d
EC
2.272 n
7.460 mn
386.6 b
1526 b
Pa-230
17.4 d
8% β-
92% β+
2.086 n
10.83 mn
204.9 b
0.023 b
Pa-231
32.76 ky
α
2.086 n
15.77 mn
580.3 b
1536 b
Pa-232
1.31 d
β-
2.086 n
23.01 mn
38.99 b
0.000 b
Pa-233
26.98 d
β-
Pa-234
6.7 h
β-
Pa-235
24.44 m
β-
Pa-236
9.1 m
β-
Pa-237
8.7 m
β-
Pa-238
2.28 m
β-
Pa-239
1.8 h
β-
Pa-240
Pa-241
Pa-242
Pa-243
Pa-244
Pa-245
Pa-246
Pa-247
Pa-248
Pa-249
Pa-250
Pa-251
Pa-252
Pa-253
Pa-254
Pa-255
Pa-256
Pa-257
Pa-258
Pa-259
Pa-260
1.813 n
11.15 mn
122.7 b
0.150 b
Th-228
1.192 y
α
2.15 n
16.21 mn
73.04 b
30.68 b
Th-229
7916 y
α
1.97 n
23.62 mn
23.79 b
0.009 b
Th-230
75.38 ky
α
2.028 n
34.53 mn
1633 b
39.99 b
Th-231
25.52 h
β-
1.851 n
49.00 mn
7.300 b
0.000 b
Th-232
14.04 Gy
α
1.813 n
74.37 mn
1292 b
15.01 b
Th-233
21.83 m
β-
1.862 n
109.6 mn
1.802 b
0.005 b
Th-234
24.10 d
mβ-
Th-235
7.2 m
β-
Th-236
37.5 m
β-
Th-237
4.8 m
β-
Th-238
9.4 m
β-
Th-239
Th-240
Th-241
Th-242
Th-243
Th-244
Th-245
Th-246
Th-247
Th-248
Th-249
Th-250
Th-251
Th-252
Th-253
Th-254
Th-255
Th-256
Th-257
Th-258
Th-259
Th-260

Notable nuclear isomers

Pa-234m
1.17 m
β-

Protactinium 234m is the exclusive decay product (99.8% of the time, at least) of thorium 234, making it a part of the uranium 238 decay chain in place of protactinium 234 (the other 0.2%), which is not produced in appreciable quantity in the decay chain of uranium 238. Due to its very short half-life, it was named "brevium" upon discovery.

3.264 n
6.659 mn
1258 b
7028 b
Am-242m
141 y
IT

Americium 242m is produced about 10% of the time from neutron capture by americium 241. Due to its long half-life, large cross section, high chance of fission, and large number of neutrons released per fission, it is a nearly ideal fuel, but cannot be made use of due to the near impossibility of separating it from the americium 241 that it must be produced from, and the low chance that any given neutron capture by americium 241 will actually produce americium 242m. The alternative, americium 242, has similarly favorable properties, although a somewhat smaller cross-section, but decays far too fast to be used.

Colors

Terminology

Units

Symbols

Data

All half-life and decay data was acquired from the various wikipedia pages for the isotopes of each element, e.g. Isotopes of Thorium

All neutronics data was acquired from wwwndc.jaea.go.jp. More specifically, it was acquired from URLs such as https://wwwndc.jaea.go.jp/cgi-bin/Tab80WWW.cgi?lib=J40&iso=U235 where the element name and mass "U235" at the end of the URL was replaced with whatever element I needed data for. For the nuclear isomers, I used "Pa234m" and "Am242m". When collecting cross-section data I used the "Maxwellian Average" column, and when collecting prompt and delayed neutron emission data I used the "0.0253-eV" column.