As useful to students and nuclear professionals as its popular predecessors, this fifth edition
provides the most up-to-date and accessible introduction to radiation detector materials …

The purpose of this communication is to describe briefly the computer programs developed
to generate the MCNP input file corresponding to any segmented tomographic data and its …

The in vivo measurement of the activity deposited in the skeleton is a very useful source of
information on human internal contaminations with transuranic elements, eg americium 241 …

The use of Monte Carlo in radiation transport is an effective way to predict absorbed dose
distributions. Monte Carlo modeling has contributed to a better understanding of photon and …

The efficiency calibration of whole-body counters (WBCs) for monitoring of internal
contaminations is usually performed with anthropomorphic physical phantoms assuming …

Whole-Body counting techniques use radiation detectors in order to evaluate the internal
exposure from radionuclides. The Whole-Body Counter (WBC) of the Greek Atomic Energy …

Determination of internal contamination of 241Am can be done by direct counting of gamma
emission using a Whole Body Counter. Due to the strong attenuation of the low-energy …

In this study, azimuthal particle redistribution (APR), and azimuthal particle rotational
splitting (APRS) methods are implemented in MCNPX2. 4 source code. First of all, the …

In vivo measurement of actinide activity in the skeleton is a valuable source of information on
human internal contamination. Estimates of skeleton activity are based on measurements of …

In vivo measurement has been widely employed to monitor internal contamination in
potentially exposed personals, wherein detection efficiency calibration is an important step …