Author: Lee, S.C.
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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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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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TUPOY019 Geant4 Simulations of Proton-induced Spallation for Applications in ADSR Systems 1943
SUPSS114   use link to see paper's listing under its alternate paper code  
  • S.C. Lee
    IIAA, Huddersfield, United Kingdom
  • C. Bungau, R. Cywinski
    University of Huddersfield, Huddersfield, United Kingdom
  Neutron spallation is an efficient process for producing intense neutron fluxes that can be exploited in Accelerator Driven Subcritical Reactors (ADSRs) for energy production and the transmutation of nuclear waste. In order to assess the feasibility of spallation driven fission and transmutation we have simulated proton induced neutron production using GEANT4, initially benchmarking our simulations against published experimental neutron spectra produced from a thick lead target bombarded with 0.5 and 1.5 GeV protons. The Bertini and INCL models available in GEANT4, coupled with the high precision (HP) neutron model, are found to adequately reproduce the published experimental data. Given the confidence in the GEANT4 simulations provided by this benchmarking we have then proceeded to simulate neutron production as a function of target geometry and thence to some preliminary studies of neutron production in an ADSR with a geometry similar to that of the proposed Belgian MYRRHA project. This paper presents the results of our GEANT4 benchmarking and simulations.  
DOI • reference for this paper ※ DOI:10.18429/JACoW-IPAC2016-TUPOY019  
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