نتایج جستجو برای: dosimetry mcnp mird
تعداد نتایج: 9022 فیلتر نتایج به سال:
Background: The formalism recommended by Task Group 60 (TG-60) of the American Association of Physicists in Medicine (AAPM) is applicable for β sources. Radioactive biocompatible and biodegradable 153Sm glass seed without encapsulation is a β- emitter with a short half life and delivers a high dose rate to the tumor in the millimeter range. In this work the dosimetry parameters of the ...
Background: Two protocols of AAPM TG-51 and IAEA TRS-398 were compared followed by a measurement and Monte Carlo simulation of beam quality correction factor, KQ, AAPM TG-51 and IAEA TRS-398 protocols were compared for the absorbed dose to water for DW, and KQ parameters. Materials and Methods: Dose measurements by either protocols were performed with cylindrical and plane parallel ch...
PURPOSE Radiopharmaceutical applications in nuclear medicine require a detailed dosimetry estimate of the radiation energy delivered to the human tissues. Over the past years, several publications addressed the problem of internal dose estimate in volumes of several sizes considering photon and electron sources. Most of them used Monte Carlo radiation transport codes. Despite the widespread use...
Introduction: The determination of patient’s absorbed dose is the first step of radiation protection which depends on the quantification of organ activity in nuclear medicine. The aim of the present study was to determine the absorbed dose by patient’s uterus following myocardial perfusion scan with 99mTC-sestamibi using Theroluminescnce dosimetry (TLD) and conjugate-view metho...
Series of mathematical phantoms of human body, given by Oak Ridge National Laboratory (ORNL), was programmed as input files for MCNP-4B code. Detailed check of geometry of these phantoms performed by MCNP-4B, discovered some minor errors, that resulted in overlapping of some organs. Three types of errors were found and described here: (a) colon overlaps with pelvis bone; (b) facial skeleton pen...
The ultimate check of the actual dose delivered to a patient in radiotherapy can only be achieved by using in vivo dosimetry. This work reports a pilot study to test the applicability of a thermoluminescent dosimetric system for performing in vivo entrance dose measurements in external photon beam radiotherapy. The measurements demonstrated the value of thermoluminescent dosimetry as a treatmen...
An innovative computational tool (DAG-MCNP) has been developed for efficient and accurate 3-D nuclear analysis of geometrically complex fusion systems. Direct coupling with CAD models allows preserving the geometrical details, eliminating possible human error, and faster design iterations. DAG-MCNP has been applied to perform 3-D nuclear analysis for several fusion designs and demonstrated the ...
The goal of this manuscript is to estimate Type B uncertainties in absorbed-dose calculations arising from the different implementations current state-of-the-art Monte Carlo codes low-energy photon cross-sections (<200 keV). simulations are carried out using three widely used domain: PENELOPE-2018, EGSnrc, and MCNP. Mass energy-absorption coefficients for water, air, graphite, their respective ...
In collaboration with the MIRD Committee, Society of Nuclear Medicine: E.E. Watson (Chair), J.S. Robertson (Task Group Leader), W.E. Bolch, A.B. Brill, N.D. Charkes, D.R. Fisher, M.T. Hays, R.W. Howell, J.A. Siegel, S.R. Thomas and B.W. Wessels Department of Nuclear and Radiological Engineering, University of Florida, Gainesville, Florida; Gaithersburg, Maryland; Department of Radiology, George...
Over the past decade, there has been progressively stronger interest in the use of a-particle emitters for radioimmunotherapy (1–6). With proper localization of the labeled antibody, the high linear energy transfer of a-particles provides a correspondingly high probability of mitotic cell kill when compared with an equivalent number of cellular traversals by lower linear energy transfer b-parti...
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