International
Tables for
Crystallography
Volume C
Mathematical, physical and chemical tables
Edited by E. Prince

International Tables for Crystallography (2006). Vol. C. ch. 4.4, p. 461

Section 4.4.6. Absorption coefficients for neutrons

B. T. M. Willish

4.4.6. Absorption coefficients for neutrons

| top | pdf |

The cross sections σ discussed in Section 4.4.4[link] represent the area of each nucleus as seen by the neutron. To calculate the beam attenuation arising from absorption it is more convenient to use the macroscopic cross section [\Sigma], which is the cross section per unit volume in units of cm−1. [\Sigma] is derived by multiplying σ for the element by the number of atoms per unit volume. Thus, for element j, with density [\rho _{j}] and atomic weight [A_{j}], [\Sigma_{j}=N_{A}\rho _{j}\sigma _{j}/A_{j},]where [N_{A}] is Avogadro's number.

Table 4.4.6.1[link] gives the macroscopic absorption cross sections [\Sigma_a] of the elements. They are tabulated for a neutron velocity v = 2200 m s−1, corresponding to a wavelength of 1.80 Å. The cross sections are larger at longer wavelengths (Section 4.4.4[link]). Apart from a few exceptions, such as boron and cadmium, the absorption cross section is vastly smaller than for X-rays. The 1/e penetration depth (l) is listed separately – most metals, for example, have a penetration depth of several cm. The data in Table 4.4.6.1[link] have been derived from the review article by Hutchings & Windsor (1987[link]).

Table 4.4.6.1| top | pdf |
Absorption of the elements for neutrons (λ = 1.80 Å)

AtomΣa (cm−1)l (cm)
H0.01410.288
D0.00006.17
He0.000120.22
Li3.26980.300
Be0.00091.059
B105.410.009
C0.00041.58
N0.06622.14
O0.00015.52
F0.00036.82
Ne0.00178.71
Na0.013510.22
Mg0.00276.11
Al0.01399.48
Si0.00858.45
P0.00618.04
S0.020816.14
Cl0.91090.731
Ar0.01432.03
K0.027918.12
Ca0.009912.35
Sc1.09060.491
Ti0.34531.74
V0.36581.35
Cr0.25581.82
Mn1.09000.789
Fe0.21740.82
Co3.34400.260
Ni0.41040.475
Cu0.32021.00
Zn0.07302.89
Ga0.14802.04
Ge0.10162.07
As0.20912.15
Se0.42921.36
Br0.16233.31
Kr0.38821.97
Rb0.004113.09
Sr0.02277.44
Y0.03883.66
Zr0.00793.42
Nb0.06402.42
Mo0.16371.75
Tc1.42810.542
Ru0.18861.48
Rh10.5440.092
Pd0.46871.29
Ag3.71200.249
Cd116.800.008
In7.41350.133
Sn0.02314.87
Sb0.16893.20
Te0.13864.01
I0.14584.36
Xe0.39042.27
Cs0.24583.57
Ba0.018913.39
La0.24022.00
Ce0.01829.60
Pr0.33332.46
Nd1.47630.496
Sm171.230.005
Eu95.7150.010
Gd1474.10.000
Tb0.73341.05
Dy29.7310.030
Ho2.07910.424
Er5.18610.182
Tm3.49190.269
Yb0.85130.717
Lu2.58890.354
Hf4.66480.195
Ta1.14340.676
W1.16090.681
Re6.16920.143
Os1.14440.442
Ir30.0640.032
Pt0.68430.682
Au5.81810.159
Hg15.1460.061
Tl0.12002.15
Pb0.00562.68
Bi0.00093.84
Ra0.17062.95
Th0.22441.68
Pa8.04050.118
U0.36501.26
Np9.05340.10
Pu14.4810.069
Am2.55220.351

References

First citation Hutchings, M. T. & Windsor, C. G. (1987). Industrial applications of neutron scattering. In Methods of experimental physics, Vol. 23, Part C, edited by K. Sköld & D. L Price. New York: Academic Press.Google Scholar








































to end of page
to top of page