Evaluation of high purity graphite sample containers for use with rapid instrumental epithermal neutron activation analysis

The suitability of graphite of spectral quality as a sample container in short irradiations for neutron activation analysis was investigated. The material is found to be a viable alternative to polyethylene containers especially in high flux irradiation positions where the properties of the latter deteriorate as a result of high neutron and gamma dose rates. Examples of application are demonstrated in epithermal neutron irradiations of biological materials and the accuracy and precision of the determinations were assessed. (author)