Calculations are presented of the effective doses per unit neutron fluence according to the ICRP publications 60 and 103. Monte Carlo N-Particle (MCNPX) code was used for six geometrical conditions of irradiation (Anterior-Posterior, Posterior-Anterior, Left-Lateral, Right-Lateral, Rotation and Isotropic) on Oak Ridge National Laboratory (ORNL) modified mathematical adult phantoms for monoenergetic neutrons from 10-9 MeV to 20 MeV. The conversion coefficients were compared with the results of an analytical phantom (Medical Internal Radiation Dose (MIRD-5)) and some voxel model (ICRP/ICRU Reference Voxel Phantom (ICRP/ICRU RVP), HANAKO, TARO and Visible Human Project (VIPMAN)). From these comparisons, one can conclude that large discrepancie...
International audienceMonte Carlo calculations are increasingly used to assess stray radiation dose ...
High resolution voxel-based phantoms were used to assess organ doses from neutron external exposure....
Recently, the International Commission on Radiological Protection (ICRP) has developed the Mesh-type...
Calculations are presented of the effective doses per unit neutron fluence according to the ICRP pub...
Monte Carlo simulations were performed to extend existing neutron personal dose equivalent fluence-t...
The fluence to organ-dose and effective-dose conversion coefficients for neutrons and protons with e...
International audienceDose equivalent limits for single organs are recommended by the ICRP (Internat...
Abstract Neutron dose coefficients for standard irradiation geometries have been repo...
This paper reviews the ICRP Publications 110 and 116 describing the reference computational phantoms...
ICRP Publication 116 on 'Conversion coefficients for radiological protection quantities for exte...
For neutron energies ranging from 1 keV to 20 MeV, the kerma coefficients for elements H, C, N, O, l...
This paper reviews the ICRP Publications 110 and 116 describing the reference computational phantoms...
With the introduction of new recommendations by ICRP Publication 103, the methodology for determinin...
Purpose: To evaluate differences in nuclear physics models of MCNPX for uncertainties in 1) the dosi...
A simple formalism has been employed to average data on neutron fluence-to-directional dose equivale...
International audienceMonte Carlo calculations are increasingly used to assess stray radiation dose ...
High resolution voxel-based phantoms were used to assess organ doses from neutron external exposure....
Recently, the International Commission on Radiological Protection (ICRP) has developed the Mesh-type...
Calculations are presented of the effective doses per unit neutron fluence according to the ICRP pub...
Monte Carlo simulations were performed to extend existing neutron personal dose equivalent fluence-t...
The fluence to organ-dose and effective-dose conversion coefficients for neutrons and protons with e...
International audienceDose equivalent limits for single organs are recommended by the ICRP (Internat...
Abstract Neutron dose coefficients for standard irradiation geometries have been repo...
This paper reviews the ICRP Publications 110 and 116 describing the reference computational phantoms...
ICRP Publication 116 on 'Conversion coefficients for radiological protection quantities for exte...
For neutron energies ranging from 1 keV to 20 MeV, the kerma coefficients for elements H, C, N, O, l...
This paper reviews the ICRP Publications 110 and 116 describing the reference computational phantoms...
With the introduction of new recommendations by ICRP Publication 103, the methodology for determinin...
Purpose: To evaluate differences in nuclear physics models of MCNPX for uncertainties in 1) the dosi...
A simple formalism has been employed to average data on neutron fluence-to-directional dose equivale...
International audienceMonte Carlo calculations are increasingly used to assess stray radiation dose ...
High resolution voxel-based phantoms were used to assess organ doses from neutron external exposure....
Recently, the International Commission on Radiological Protection (ICRP) has developed the Mesh-type...