Thorium metal was irradiated in the thermal neutron flux of the Low Intensity Test Reactor and of a graphite reactor. From mass spectrographic analysis of the U234 content and assumption of an effective capture cross section (including epithermal as well as thermal neutron capture) of 8.0 barns for Th232, the effective neutron capture cross section of Pa233 for thermal reactor neutrons was determined to be 140 ± 20 barns.