نتایج جستجو برای: iridium_192 monte carlo mcnp

تعداد نتایج: 72882  

1996
J. C. Liu S. Rokni V. Vylet R. Arora A. Justus

Neutron detection time distribution is an important factor for the dead-time correction for moderator type neutron detectors used in pulsed radiation fields. Measurements of the neutron detection time distributions of multisphere LiI detectors (2Ó, 3Ó, 5Ó, 8Ó, 10Ó and 12Ó in diameter) and AB remmeter were made inside a ANL 20-MeV electron Linac room. Calculations of the neutron detection time d...

2018
Hao Sun Chenglong Wang Xiao Liu Wenxi Tian Suizheng Qiu Guanghui Su

Underwater vehicle is designed to ensure the security of country sea boundary, providing harsh requirements for its power system design. Conventional power sources, such as battery and Stirling engine, are featured with low power and short lifetime. Micronuclear reactor power source featured with higher power density and longer lifetime would strongly meet the demands of unmanned underwater veh...

2009
Kimberly A. Burns L. Eric Smith Christopher J. Gesh Mark W. Shaver

The accurate and efficient simulation of coupled neutron-photon problems is necessary for several important radiation detection applications. Examples include the detection of nuclear threats concealed in cargo containers and prompt gamma neutron activation analysis for nondestructive determination of elemental composition of unknown samples. In these applications, highresolution gamma-ray spec...

2007
Yunlin Xu Marek Flaska Sara Pozzi Vladimir Protopopescu Thomas Downar

In this paper, we present a neutron spectrum unfolding technique based on a modification of the least-squares method. The main innovation is the use of a Krylov subspace iteration method to solve the least-squares normal equations. This method was employed because it performs better on ill-conditioned systems of linear equations as compared with standard direct-solution methods. Three different...

2005
Robert L. Metzger Kenneth A. Van Riper

A Monte Carlo shielding model for PET/CT clinics Robert L. Metzger and Kenneth A. Van Riper Radiation Safety Engineering, Inc Chandler, AZ Abstract Modern PET/CT clinics consist of a scanner room housing the double gantry PET/CT unit and a control area, two or more quiet rooms where patients rest prior to scanning, and a hot lab where doses are prepared. Of these areas, the scanner room, quiet ...

2001
Nadia Messaoudi Edouard Mbala Malambu

Current calculation methods and nuclear data are well validated for conventional nuclear reactor systems. However there is a further need for validating the computational tools and the nuclear data for ADS applications. The OECD/NEA, in co-operation with CIEMAT (Spain) and CEA (France), therefore launched a benchmark based on the MUSE-4 experiments being carried out at Cadarache, France, to sim...

Journal: :Radiation protection dosimetry 2011
G Gialousis A Dimitriadis E Yakoumakis

Lung brachytherapy using high-dose rate (192)Ir technique is a well-established technique of radiation therapy. However, many commercial treatment planning systems do not have the ability to consider the inhomogeneity of lung in relation to normal tissue. Under such circumstances dose calculations for tissues and organs at risk close to the target are inaccurate. The purpose of the current stud...

Journal: :journal of medical signals and sensors 0
keivan jabbari hossein saberi anvar mohammad bagher tavakoli alireza amouheidari

background: the monte carlo method is the most accurate method for simulation of radiation therapy equipment. the linear accelerators are currently the most widely used machines in radiation therapy centers. methods: in this work, a monte carlo modelling of the siemens oncor linear accelerator in 6 mv and 18 mv beams was performed. the results of simulation were validated by measurements in wat...

Journal: :Medical physics 2009
Hélio Yoriyaz Maurício Moralles Paulo de Tarso Dalledone Siqueira Carla da Costa Guimarães Felipe Belonsi Cintra Adimir dos Santos

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...

2009
M. E. Sawan B. Kiedrowski B. Smith A. Ibrahim R. Slaybaugh E. P. Marriott

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 ...

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