[en] The immediate objectives of this program are to measure the spectrum-integrated helium generation rates and cross sections of several materials in the available high intensity neutron sources, and to develop neutron dosimetry procedures using some of these materials. This requires further development of foil activation dosimetry techniques, since the cross section measurements require a detailed characterization of each neutron environment. The neutron facilities presently used in this program include accelerators producing d-T and d-Be reactions and high flux mixed-spectrum fission reactors. Most of the work reported here has focused on neutron spectra from the d-T reaction. A description is given of the preliminary analysis of wire rings included in the irradiation capsule for helium accumulation fluence dosimetry. The results show non-uniformities in the neutron fluence distribution characterizing this irradiation, and point out the value of helium accumulation fluence dosimetry for characterizing high energy (approximately 5 to 30 MeV) neutron fields. The helium accumulation fluence data are being used to adjust the neutron fluence map for calculation of final helium generation cross sections from the other RTNS-irradiated pure element specimens. Most of the specimens irradiated in the RTNS-I experiment have been analyzed for helium, and preliminary results are presented