scholarly journals Response assessment of a new albedo neutron dosimeter

2018 ◽  
Vol 48 ◽  
pp. 1860111
Author(s):  
Silvia Barros ◽  
Geehyun Kim
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Simulations ◽  
Human Body ◽  
State Of The Art ◽  
Response Assessment ◽  
Dose Estimation ◽  
Neutron Detectors ◽  
Thermoluminescent Dosimeters ◽  
Neutron Dosimeter ◽  
Mcnpx Code

The use of thermoluminescent dosimeters (TLDs) by personnel who work in radiation-rich environments is required by law. However, many professionals prefer to use Electronic Personal Dosimeters (EPDs), which provide dose estimation in real time. This preference may lead to a generalized use of the EPD instead of using the required TLD, as the use of both types at once can be uncomfortable and impractical. In an effort to avoid this scenario, a gamma/neutron dosimeter composed of a TLD and an EPD is being developed. In this paper, the results obtained from the studies performed in order to develop the neutron albedo dosimeter to be incorporated in the TLD[Formula: see text]EPD dosimeter are presented. Monte Carlo simulations using the state-of-the-art Monte Carlo N-Particle Transport (MCNPX) code were used to calculate the response of the albedo dosimeter. The thermal neutron detectors under consideration for use in the proposed dosimeter are the EJ-426 and the EJ-420. Both detectors employ a lithium compoundenriched to 95% [Formula: see text]Li dispersed in a ZnS:(Ag) matrix. The tomographic phantom Korean Typical Man-2 was used in the simulations to calculate the fraction of radiation backscattered by a human body in different radiation field conditions. From these results, it was concluded that both dosimeters are fit to be used as albedo dosimeters.

scholarly journals Portable multi-node LQCD Monte Carlo simulations using OpenACC

2018 ◽  
Vol 29 (01) ◽  
pp. 1850010 ◽  
Author(s):  
Claudio Bonati ◽  
Enrico Calore ◽  
Massimo D’Elia ◽  
Michele Mesiti ◽  
Francesco Negro ◽  
...  
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Simulations ◽  
Parallel Programming ◽  
Programming Model ◽  
State Of The Art ◽  
Computer Architectures ◽  
Monte Carlo Code ◽  
Processor Architectures ◽  
Parallel Programming Model ◽  
High Level

This paper describes a state-of-the-art parallel Lattice QCD Monte Carlo code for staggered fermions, purposely designed to be portable across different computer architectures, including GPUs and commodity CPUs. Portability is achieved using the OpenACC parallel programming model, used to develop a code that can be compiled for several processor architectures. The paper focuses on parallelization on multiple computing nodes using OpenACC to manage parallelism within the node, and OpenMPI to manage parallelism among the nodes. We first discuss the available strategies to be adopted to maximize performances, we then describe selected relevant details of the code, and finally measure the level of performance and scaling-performance that we are able to achieve. The work focuses mainly on GPUs, which offer a significantly high level of performances for this application, but also compares with results measured on other processors.

scholarly journals Monte-Carlo simulations of natural uranium setups irradiated with relativistic deuterons by means of MCNPX code

2013 ◽  
Author(s):  
Martin Suchopar ◽  
Vladimir Wagner ◽  
Jitka Vrzalova ◽  
Ondrej Svoboda ◽  
Jindra Adam ◽  
...  
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Simulations ◽  
Natural Uranium ◽  
Mcnpx Code

Verification of dose estimation of Auger electrons emitted from Cu-64 using a combination of FNTD measurements and Monte Carlo simulations

2020 ◽  
Vol 132 ◽  
pp. 106256 ◽  
Author(s):  
Tamon Kusumoto ◽  
Yusuke Matsuya ◽  
Kentaro Baba ◽  
Ryo Ogawara ◽  
Mark S. Akselrod ◽  
...  
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Simulations ◽  
Dose Estimation ◽  
Auger Electrons

scholarly journals Development of techniques based on Monte Carlo simulations for clearance of Co-57 and Ge-68/Ga-68 sealed radioactive sources

2019 ◽  
Vol 26 ◽  
pp. 194
Author(s):  
Tatiana Siarafera ◽  
Eleni Ntalla ◽  
Dimitris Mavrikis ◽  
Angelos Markopoulos ◽  
Alexandra Ioannidou ◽  
...  
Keyword(s):  
Monte Carlo Simulation ◽  
Monte Carlo ◽  
Nuclear Medicine ◽  
Monte Carlo Simulations ◽  
Pet Imaging ◽  
Gamma Camera ◽  
Mcnpx Code ◽  
Specific Source ◽  
Useful Life ◽  
Radioactive Sources

Sealed radioactive sources of Co-57 and Ge-68/Ga-68 are used for the calibration of various nuclear medicine systems like Gamma camera and PET imaging. After their useful life, these sealed sources need to be kept in control for decay until meeting the general clearance criterion. The aim of this work is to determine the activity of spent sealed radioactive sources of Ge-68 / Ga-68 and Co-57. For this purpose, techniques based on Monte Carlo simulation by the use of the MCNPX code was developed for evaluation of the 3”x3” NaI(Tl) scintillator efficiency for specific source–detector geometries. These techniques proved to be accurate. 

RF and DC characterization of state-of-the-art GaN HEMT devices through cellular Monte Carlo simulations

2010 ◽  
Vol 7 (10) ◽  
pp. 2445-2449
Author(s):  
Fabio Alessio Marino ◽  
Diego Guerra ◽  
Stephen Goodnick ◽  
David Ferry ◽  
Marco Saraniti
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Simulations ◽  
State Of The Art ◽  
Gan Hemt ◽  
Cellular Monte Carlo ◽  
Dc Characterization
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