Experimental verification of radiation dose in mixed neutron/gamma radiation fields

The TRIGA research reactor at Jozef Stefan Institute is used for irradiation of various samples. The Monte Carlo code for transport of neutrons and photons, MCNP, was used to calculate dose rates in irradiation channels in the operating TRIGA research reactor. Several measurements of dose rates in individual irradiation channels were performed with CaF2 and LiF TLDs. The calculated dose rates significantly differ from the measured ones especially for the neutron dose rate. The second experimental method used was tooth enamel dosimetry. Results indicate that human teeth are suitable for radiation dose assessment in mixed neutron/gamma radiation fields with dose rates of several Gy per second. (author)