[en] Prompt gamma-ray spectroscopy is used in a wide variety of applications for determining material compositions. High-quality photon-production data from thermal-neutron capture reactions are essential for these applications. Radiation transport codes, such as MCNP^TM, are often used to design detector systems, determine minimum detection thresholds, etc. These transport codes rely on evaluated nuclear databases such as ENDF (Evaluated Nuclear Data File) to provide the fundamental data used in the transport calculations. Often the photon-production data from incident neutron reactions in the evaluations are of relatively poor quality. We have compiled the best experimental data for thermal-neutron capture for the naturally occurring isotopes for elements from hydrogen through zinc as well as for ^{70,72,73,74,76}Ge, ¹⁴⁹Sm, ^155,157Gd, ¹⁸¹Ta and ^{182,183,184,186}W. This compilation has been used to update the ENDF evaluations for ¹H, ⁴He, ⁹Be, ¹⁴N, ¹⁶O, ¹⁹F, Na, Mg, ²⁷Al, ³²S, S, ^35,37Cl, K, Ca, ⁴⁵Sc, Ti, ⁵¹V, ^50,52,53,54Cr, ⁵⁵Mn, ^54,56,57,58Fe, ^{58,60,61,62,64}Ni, ^63,65Cu and ^{182,183,184,186}W. In addition, the inelastic cross sections and corresponding secondary-photon distributions were updated for ¹⁶0. Complete new evaluations were submitted to ENDF for ^35,37Cl. This report briefly describes the compilation process and the changes made to the ENDF evaluations. (author)