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Endo, Akira
Annals of the ICRP, 45(1_suppl.), p.178 - 187, 2016/06
The protection quantities, equivalent dose in an organ or tissue and effective dose, were developed by ICRP to allow quantification of the extent of exposure of the human body to ionizing radiation to be used for the implementation of the limitation and optimization principles. The body-related protection quantities are not measurable in practice. Therefore, ICRU developed a set of operational dose quantities for use in radiation measurements for external radiations that provide assessment of the protection quantities. ICRU has examined the rationale for operational quantities taking into account the changes in the definitions of the protection quantities in the ICRP 2007 Recommendations. The committee has investigated a set of alternative definitions for operational quantities different to the existing quantities. The major change in the currently favoured set of quantities is the redefinition of the operational quantities for area monitoring from being based on doses at a point in the ICRU sphere to ones based on particle fluence and the relationship to the protection quantities.
Endo, Akira; Hamada, Nobuyuki*
Isotope News, (745), p.42 - 43, 2016/06
ICRP Symposium on Radiological Protection Dosimetry was held in Hongo campus, the University of Tokyo on February 18, 2016. Committee 2 of the International Commission on Radiological Protection (ICRP) is engaged in the development of dose coefficients for the assessment of internal and external radiation exposures; development of reference biokinetic and dosimetric models, and reference data for workers and members of the public. The symposium aimed at reviewing the current work of ICRP and discussing research needed for the ICRP System of radiological protection dosimetry. This article reviews the presentations and discussion in the symposium.
Furuta, Takuya; Takahashi, Fumiaki
Radiation Protection Dosimetry, 167(4), p.392 - 398, 2015/12
Times Cited Count：7 Percentile：51.25(Environmental Sciences)A new approach was proposed to compute radiation dose to objects of interest in infinitely expanded radiation fields with Monte Carlo transport codes. The particles, which were emitted from the location far from the interested object, could be effectively taken into account by setting reflection boundaries at the borders of the computational area in the newly developed method. Here, the positions and momenta of the particles at each reflection were recorded and used as the sources to simulate particles from the exterior region of the computational area. The validity of new method was checked by radiation transport calculations of objects on the infinitely expanded contaminated ground surface. The results in our new approach agreed within statistical errors of the simulation with those in the conventional approach considering a very large computational area. In addition, an efficiency in computational time was compared between the new and conventional approaches.
Onodera, Junichi;
IAEA-CN-54/65P, 0, p.306 - 309, 1996/00
no abstracts in English
Yamamoto, Hideaki
Proc. of IAEA/KINS Nuclear Safety Symp., 0, p.26 - 31, 1996/00
no abstracts in English
