Dosimetry cross sections are fundamental quantities for proper determination of the neutron fluences in points interest under heavy radiation load. One critical applications is Reactor Pressure Vessel aging management, related to correct estimation its residual lifetime or many non-reactor including dosimetry accelerator-based fields space applications. The flux neutrons above 12 MeV reference ...

The epithermal neutron beam model of the Finnish boron neutron capture therapy (BNCT) facility (FiR 1) was created using the two-dimensional (2D) discrete ordinates transport (DORT) code. The final design of the beam was achieved using the DORT model: the optimal thickness of the neutron moderator and the length and the thickness of the bismuth collimator of the beam were calculated. The final ...

Several methods for determining by persons accidentally exposed the dose received to a criticality ekc&sion have been in;est;gated. The dosimet~ methods included use of film badges, thermoluminescent dosimeters, threshold detector units, Hurst proportional neutron counters, 10-in.-sphere neutron detectors, the multisphere technique, bloodsodium activation, and Geiger counter readings at the abd...

Out-of-field doses from radiotherapy can cause harmful side effects or eventually lead to secondary cancers. Scattered doses outside the applicator field, neutron source strength values, and neutron dose equivalents have not been broadly investigated for high-energy electron beams. To better understand the extent of these exposures, we measured out-of-field dose characteristics of electron appl...

If the neutron fields at personnel workplaces differ from in which individual dosimeters are verified, there is a possibility of additional errors assessment such dosimetric quantities as ambient dose equivalent, equivalent or effective dose. To take into account energy distribution radiation flux density and geometry irradiation workers, it necessary to study characteristics personnel. In orde...

A high-energy photon beam that is more than 10 MV can produce neutron contamination. Neutrons are generated by the [γ,n] reactions with a high-Z target material. The equivalent neutron dose and gamma dose from activation products have been estimated in a LINAC equipped with a 15-MV photon beam. A Monte Carlo simulation code was employed for neutron and photon dosimetry due to mixed beam. The ne...