IPAC2016 - List of Authors (Barlow, R.J.)

Paper	Title	Page
TUPOY017	Beam Energy Deposition from PS Booster and Production Rates of Selected Medical Radioisotopes in the CERN-MEDICIS Target	1936
	B.C. Gonsalves, R.J. Barlow, S.C. Lee IIAA, Huddersfield, United Kingdom R.M. Dos Santos Augusto LMU, München, Germany T. Stora CERN, Geneva, Switzerland
	CERN-MEDICIS uses the scattered (ca. 90%) 1.4 GeV, 2 uA protons delivered by the PS Booster to the ISOLDE target, which would normally end up in the beam dump. After irradiation, the MEDICIS target is transported back to an offline isotope mass separator, where the produced isotopes are mass separated, and are then collected. The required medical radioisotopes are later chemically separated in the class A laboratory. The radioisotopes are transported to partner hospitals for processing and preparation for medical use, imaging or therapy. Production of the isotopes is affected by the designs of the ISOLDE and MEDICIS targets. The MEDICIS target unit is a configurable unit, allowing for variations in target material as well as ion source for the production of selected medical radioisotopes. The energy deposition on both targets is simulated using the Monte Carlo code FLUKA, along with the in-beam production of some medical isotopes of interest. Diffusion and effusion efficiencies are then applied to estimate their production.
DOI •	reference for this paper ※ DOI:10.18429/JACoW-IPAC2016-TUPOY017
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TUPOY021	Characterisation of the Spectra of Spallation Neutron Sources through Modelling	1950
	R.J. Barlow, A. Rummana IIAA, Huddersfield, United Kingdom R. Seviour University of Huddersfield, Huddersfield, United Kingdom
	We characterise the neutron flux and energy spectra produced by protons on a lead target. This may enable studies of the neutronics of an ADSR, to be separated from the higher energy spallation processes, in order to explore te potential of ADSR as a better alternative for energy production, safety and waste transmutation. We consider a range of proton energies, and show how the numbers of neutrons produced can be fitted by some simple functions of the proton energy, as can the spatial and energy distributions. These calculations were performed in both MCNPX and Geant4 and we compare and benchmark the low energy neutron spectra obtained by MCNPX code and a Monte Carlo Code Geant4 against each other. Discrepancies were found for the low energy neutron spectrum, but by using different models as calculation options for low energy neutrons in Geant4, this disagreement has been significantly reduced.
DOI •	reference for this paper ※ DOI:10.18429/JACoW-IPAC2016-TUPOY021
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TUPOY018	FLUKA Simulations for Radiation Protection at 3 Different Facilities	1940
	R. Rata, S.C. Lee IIAA, Huddersfield, United Kingdom R.J. Barlow University of Huddersfield, Huddersfield, United Kingdom
	FLUKA Monte Carlo Code is a transport code widely used in radiation protection studies. The code was developed in 1962 by Johannes Ranft and the name stands for FLUktuierende Kaskade (Fluctuating Cascade). The code was developede for high-energy physics and it can track 60 different particles from 1keV to thousands of TeV. It can be applied to accelerator design, shielding design, dosimetry, space radiation and hadron therapy. For particle therapy, FLUKA uses various physical models, all implemented in the PEANUT (Pre-Equilibrium Approach to Nuclear Thermalization) framework. The investigation was made for three different facilities : the Clatterbridge Cancer Centre, the Christie Hospital and the OpenMeD facility at CERN. We calculated the secondary dose distributed to the patient, in case of Clatterbridge Cancer Centre, and to the workers in case of the Christie Hospital and OpenMeD, and to investigate whether the shielding methods meet the existing radiation protection requirements and that the doses to the staff are kept As Low As Reasonably Achievable (ALARA).
DOI •	reference for this paper ※ DOI:10.18429/JACoW-IPAC2016-TUPOY018
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TUPOY023	A Compact and High Current FFAG for the Production of Radioisotopes for Medical Applications	1957
	D. Bruton, R.J. Barlow, T.R. Edgecock, R. Seviour University of Huddersfield, Huddersfield, United Kingdom C. Johnstone PAC, Batavia, Illinois, USA
	A low energy Fixed Field Alternating Gradient (FFAG) accelerator has been designed for the production of radioisotopes. Tracking studies have been conducted using the OPAL code, including the effects of space charge. Radioisotopes have a wide range of uses in medicine, and recent disruption to the supply chain has seen a renewed effort to find alternative isotopes and production methods. The design features separate sector magnets with non-scaling, non-linear field gradients but without the counter bends commonly found in FFAG's. The machine is isochronous at the level of 0.3% up to at least 28 MeV and hence able to operate in Continuous Wave (CW) mode. Both protons and helium ions can be used with this design and it has been demonstrated that proton beams with currents of up to 20 mA can be accelerated. An interesting option for the production of radioisotopes is the use of a thin internal target. We have shown that this design has large acceptance, ideal for allowing the beam to be recirculated through the target many times, the lost energy being restored on each cycle. In this way, the production of Technetium-99m, for example, can take place at the optimum energy.
DOI •	reference for this paper ※ DOI:10.18429/JACoW-IPAC2016-TUPOY023
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Paper

Title

Page

Beam Energy Deposition from PS Booster and Production Rates of Selected Medical Radioisotopes in the CERN-MEDICIS Target

1936

B.C. Gonsalves, R.J. Barlow, S.C. Lee
IIAA, Huddersfield, United Kingdom
R.M. Dos Santos Augusto
LMU, München, Germany
T. Stora
CERN, Geneva, Switzerland

CERN-MEDICIS uses the scattered (ca. 90%) 1.4 GeV, 2 uA protons delivered by the PS Booster to the ISOLDE target, which would normally end up in the beam dump. After irradiation, the MEDICIS target is transported back to an offline isotope mass separator, where the produced isotopes are mass separated, and are then collected. The required medical radioisotopes are later chemically separated in the class A laboratory. The radioisotopes are transported to partner hospitals for processing and preparation for medical use, imaging or therapy. Production of the isotopes is affected by the designs of the ISOLDE and MEDICIS targets. The MEDICIS target unit is a configurable unit, allowing for variations in target material as well as ion source for the production of selected medical radioisotopes. The energy deposition on both targets is simulated using the Monte Carlo code FLUKA, along with the in-beam production of some medical isotopes of interest. Diffusion and effusion efficiencies are then applied to estimate their production.

DOI •

reference for this paper ※ DOI:10.18429/JACoW-IPAC2016-TUPOY017

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TUPOY021

Characterisation of the Spectra of Spallation Neutron Sources through Modelling

1950

R.J. Barlow, A. Rummana
IIAA, Huddersfield, United Kingdom
R. Seviour
University of Huddersfield, Huddersfield, United Kingdom

We characterise the neutron flux and energy spectra produced by protons on a lead target. This may enable studies of the neutronics of an ADSR, to be separated from the higher energy spallation processes, in order to explore te potential of ADSR as a better alternative for energy production, safety and waste transmutation. We consider a range of proton energies, and show how the numbers of neutrons produced can be fitted by some simple functions of the proton energy, as can the spatial and energy distributions. These calculations were performed in both MCNPX and Geant4 and we compare and benchmark the low energy neutron spectra obtained by MCNPX code and a Monte Carlo Code Geant4 against each other. Discrepancies were found for the low energy neutron spectrum, but by using different models as calculation options for low energy neutrons in Geant4, this disagreement has been significantly reduced.

DOI •

reference for this paper ※ DOI:10.18429/JACoW-IPAC2016-TUPOY021

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TUPOY018

FLUKA Simulations for Radiation Protection at 3 Different Facilities

1940

R. Rata, S.C. Lee
IIAA, Huddersfield, United Kingdom
R.J. Barlow
University of Huddersfield, Huddersfield, United Kingdom

FLUKA Monte Carlo Code is a transport code widely used in radiation protection studies. The code was developed in 1962 by Johannes Ranft and the name stands for FLUktuierende Kaskade (Fluctuating Cascade). The code was developede for high-energy physics and it can track 60 different particles from 1keV to thousands of TeV. It can be applied to accelerator design, shielding design, dosimetry, space radiation and hadron therapy. For particle therapy, FLUKA uses various physical models, all implemented in the PEANUT (Pre-Equilibrium Approach to Nuclear Thermalization) framework. The investigation was made for three different facilities : the Clatterbridge Cancer Centre, the Christie Hospital and the OpenMeD facility at CERN. We calculated the secondary dose distributed to the patient, in case of Clatterbridge Cancer Centre, and to the workers in case of the Christie Hospital and OpenMeD, and to investigate whether the shielding methods meet the existing radiation protection requirements and that the doses to the staff are kept As Low As Reasonably Achievable (ALARA).

DOI •

reference for this paper ※ DOI:10.18429/JACoW-IPAC2016-TUPOY018

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TUPOY023

A Compact and High Current FFAG for the Production of Radioisotopes for Medical Applications

1957

D. Bruton, R.J. Barlow, T.R. Edgecock, R. Seviour
University of Huddersfield, Huddersfield, United Kingdom
C. Johnstone
PAC, Batavia, Illinois, USA

A low energy Fixed Field Alternating Gradient (FFAG) accelerator has been designed for the production of radioisotopes. Tracking studies have been conducted using the OPAL code, including the effects of space charge. Radioisotopes have a wide range of uses in medicine, and recent disruption to the supply chain has seen a renewed effort to find alternative isotopes and production methods. The design features separate sector magnets with non-scaling, non-linear field gradients but without the counter bends commonly found in FFAG's. The machine is isochronous at the level of 0.3% up to at least 28 MeV and hence able to operate in Continuous Wave (CW) mode. Both protons and helium ions can be used with this design and it has been demonstrated that proton beams with currents of up to 20 mA can be accelerated. An interesting option for the production of radioisotopes is the use of a thin internal target. We have shown that this design has large acceptance, ideal for allowing the beam to be recirculated through the target many times, the lost energy being restored on each cycle. In this way, the production of Technetium-99m, for example, can take place at the optimum energy.

DOI •

reference for this paper ※ DOI:10.18429/JACoW-IPAC2016-TUPOY023

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