Modeling complex vapor-transport systems using Monte-Carlo techniques: Radioactive ion beam applications

2005 ◽  
Vol 23 (6) ◽  
pp. 1558-1567 ◽  
Author(s):  
Y. Zhang ◽  
G. D. Alton
Keyword(s):  
Monte Carlo ◽  
Ion Beam ◽  
Vapor Transport ◽  
Transport Systems ◽  
Radioactive Ion Beam ◽  
Monte Carlo Techniques

scholarly journals Radiation protection considerations along a radioactive ion beam transport line

2016 ◽  
Vol 44 ◽  
pp. 1660238 ◽  
Author(s):  
Lucia Sarchiapone ◽  
Demetre Zafiropoulos
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Simulations ◽  
Radiation Protection ◽  
Ion Beam ◽  
Radioactive Beam ◽  
High Mass ◽  
Radioactive Ion Beam ◽  
Decay Times ◽  
Pass Through ◽  
A Charge

The goal of the SPES project is to produce accelerated radioactive ion beams for Physics studies at “Laboratori Nazionali di Legnaro” (INFN, Italy). This accelerator complex is scheduled to be built by 2016 for an effective operation in 2017. Radioactive species are produced in a uranium carbide target, by the interaction of 200 [Formula: see text]A of protons at 40 MeV. All of the ionized species in the 1+ state come out of the target (ISOL method), and pass through a Wien filter for a first selection and an HMRS (high mass resolution spectrometer). Then they are transported by an electrostatic beam line toward a charge state breeder (where the 1[Formula: see text] to n[Formula: see text] multi-ionization takes place) before selection and reacceleration at the already existing superconducting linac. The work concerning dose evaluations, activation calculation, and radiation protection constraints related to the transport of the radioactive ion beam (RIB) from the target to the mass separator will be described in this paper. The FLUKA code has been used as tool for those calculations needing Monte Carlo simulations, in particular for the evaluation of the dose rate due to the presence of the radioactive beam in the selection/interaction points. The time evolution of a radionuclide inventory can be computed online with FLUKA for arbitrary irradiation profiles and decay times. The activity evolution is analytically evaluated through the implementation of the Bateman equations. Furthermore, the generation and transport of decay radiation (limited to gamma, beta- and beta[Formula: see text] emissions) is possible, referring to a dedicated database of decay emissions using mostly information obtained from NNDC, sometimes supplemented with other data and checked for consistency. When the use of Monte Carlo simulations was not feasible, the Bateman equations, or possible simplifications, have been used directly.

A SINGLE STAGE ECR SOURCE FOR THE RADIOACTIVE ION BEAM PROJECT IN LOUVAIN-LA-NEUVE

1989 ◽  
Vol 50 (C1) ◽  
pp. C1-813-C1-817
Author(s):  
M. ARNOULD ◽  
F. BAETEN ◽  
D. DARQUENNES ◽  
Th. DELBAR ◽  
C. DOM ◽  
...  
Keyword(s):  
Ion Beam ◽  
Single Stage ◽  
Radioactive Ion Beam ◽  
Ecr Source

Scientific program of DERICA — prospective accelerator and storage ring facility for radioactive ion beam research

2018 ◽  
Vol 189 (07) ◽  
pp. 721-738
Author(s):  
Leonid V. Grigorenko ◽  
Boris Yu. Sharkov ◽  
Andrei S. Fomichev ◽  
Aleksei L. Barabanov ◽  
V. Bart ◽  
...  
Keyword(s):  
Storage Ring ◽  
Ion Beam ◽  
Scientific Program ◽  
Radioactive Ion Beam ◽  
And Storage

Bayesian Estimation of DSGE Models

2015 ◽  
Author(s):  
Edward P. Herbst ◽  
Frank Schorfheide
Keyword(s):  
Monte Carlo ◽  
Sequential Monte Carlo ◽  
Likelihood Function ◽  
Academic Research ◽  
Dynamic Stochastic General Equilibrium ◽  
Computational Techniques ◽  
Dsge Models ◽  
Monte Carlo Techniques ◽  
Dynamic Stochastic ◽  
Theoretical Foundations

Dynamic stochastic general equilibrium (DSGE) models have become one of the workhorses of modern macroeconomics and are extensively used for academic research as well as forecasting and policy analysis at central banks. This book introduces readers to state-of-the-art computational techniques used in the Bayesian analysis of DSGE models. The book covers Markov chain Monte Carlo techniques for linearized DSGE models, novel sequential Monte Carlo methods that can be used for parameter inference, and the estimation of nonlinear DSGE models based on particle filter approximations of the likelihood function. The theoretical foundations of the algorithms are discussed in depth, and detailed empirical applications and numerical illustrations are provided. The book also gives invaluable advice on how to tailor these algorithms to specific applications and assess the accuracy and reliability of the computations. The book is essential reading for graduate students, academic researchers, and practitioners at policy institutions.

Neutron dose evaluation of Elekta Linac at two energies (10 & 18 MV) by MCNP code and comparison with experimental measurements

2014 ◽  
Vol 6 (1) ◽  
pp. 1006-1015
Author(s):  
Negin Shagholi ◽  
Hassan Ali ◽  
Mahdi Sadeghi ◽  
Arjang Shahvar ◽  
Hoda Darestani ◽  
...  
Keyword(s):  
Monte Carlo ◽  
Measurement Data ◽  
Calculated Data ◽  
High Energy ◽  
Neutron Dose ◽  
Dose Assessment ◽  
Photon Flux ◽  
Dose Equivalent ◽  
Monte Carlo Techniques ◽  
Neutron Dose Equivalent

Medical linear accelerators, besides the clinically high energy electron and photon beams, produce other secondary particles such as neutrons which escalate the delivered dose. In this study the neutron dose at 10 and 18MV Elekta linac was obtained by using TLD600 and TLD700 as well as Monte Carlo simulation. For neutron dose assessment in 2020 cm2 field, TLDs were calibrated at first. Gamma calibration was performed with 10 and 18 MV linac and neutron calibration was done with 241Am-Be neutron source. For simulation, MCNPX code was used then calculated neutron dose equivalent was compared with measurement data. Neutron dose equivalent at 18 MV was measured by using TLDs on the phantom surface and depths of 1, 2, 3.3, 4, 5 and 6 cm. Neutron dose at depths of less than 3.3cm was zero and maximized at the depth of 4 cm (44.39 mSvGy-1), whereas calculation resulted  in the maximum of 2.32 mSvGy-1 at the same depth. Neutron dose at 10 MV was measured by using TLDs on the phantom surface and depths of 1, 2, 2.5, 3.3, 4 and 5 cm. No photoneutron dose was observed at depths of less than 3.3cm and the maximum was at 4cm equal to 5.44mSvGy-1, however, the calculated data showed the maximum of 0.077mSvGy-1 at the same depth. The comparison between measured photo neutron dose and calculated data along the beam axis in different depths, shows that the measurement data were much more than the calculated data, so it seems that TLD600 and TLD700 pairs are not suitable dosimeters for neutron dosimetry in linac central axis due to high photon flux, whereas MCNPX Monte Carlo techniques still remain a valuable tool for photonuclear dose studies.

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