@article{NiedermeierPennerUsherovichetal.2023, author = {Niedermeier, Jana and Penner, Crystal and Usherovich, Samuel and B{\´e}langer-Champagne, Camille and Paulßen, Elisabeth and Cornelia, Hoehr}, title = {Optical Fibers as Dosimeter Detectors for Mixed Proton/Neutron Fields - A Biological Dosimeter}, series = {electronics}, volume = {12}, journal = {electronics}, number = {2}, publisher = {MDPI}, address = {Basel}, issn = {2079-9292}, doi = {10.3390/electronics12020324}, pages = {11 Seiten}, year = {2023}, abstract = {In recent years, proton therapy has gained importance as a cancer treatment modality due to its conformality with the tumor and the sparing of healthy tissue. However, in the interaction of the protons with the beam line elements and patient tissues, potentially harmful secondary neutrons are always generated. To ensure that this neutron dose is as low as possible, treatment plans could be created to also account for and minimize the neutron dose. To monitor such a treatment plan, a compact, easy to use, and inexpensive dosimeter must be developed that not only measures the physical dose, but which can also distinguish between proton and neutron contributions. To that end, plastic optical fibers with scintillation materials (Gd₂O₂S:Tb, Gd₂O₂S:Eu, and YVO₄:Eu) were irradiated with protons and neutrons. It was confirmed that sensors with different scintillation materials have different sensitivities to protons and neutrons. A combination of these three scintillators can be used to build a detector array to create a biological dosimeter.}, language = {en} } @article{TrappLammersEngudaretal.2023, author = {Trapp, Svenja and Lammers, Tom and Engudar, Gokce and Hoehr, Cornelia and Denkova, Antonia G. and Paulßen, Elisabeth and de Kruijff, Robin M.}, title = {Membrane-based microfluidic solvent extraction of Ga-68 from aqueous Zn solutions: towards an automated cyclotron production loop}, series = {EJNMMI Radiopharmacy and Chemistry}, volume = {2023}, journal = {EJNMMI Radiopharmacy and Chemistry}, number = {8, Article number: 9}, publisher = {Springer Nature}, issn = {2365-421X}, doi = {10.1186/s41181-023-00195-2}, pages = {1 -- 14}, year = {2023}, language = {en} } @article{PennerUsherovichNiedermeieretal.2022, author = {Penner, Crystal and Usherovich, Samuel and Niedermeier, Jana and B{\´e}langer-Champagne, Camille and Trinczek, Michael and Paulßen, Elisabeth and Hoehr, Cornelia}, title = {Organic Scintillator-Fibre Sensors for Proton Therapy Dosimetry: SCSF-3HF and EJ-260}, series = {electronics}, volume = {12}, journal = {electronics}, number = {1}, publisher = {MDPI}, address = {Basel}, issn = {2079-9292}, doi = {10.3390/electronics12010011}, pages = {12 Seiten}, year = {2022}, abstract = {In proton therapy, the dose from secondary neutrons to the patient can contribute to side effects and the creation of secondary cancer. A simple and fast detection system to distinguish between dose from protons and neutrons both in pretreatment verification as well as potentially in vivo monitoring is needed to minimize dose from secondary neutrons. Two 3 mm long, 1 mm diameter organic scintillators were tested for candidacy to be used in a proton-neutron discrimination detector. The SCSF-3HF (1500) scintillating fibre (Kuraray Co. Chiyoda-ku, Tokyo, Japan) and EJ-260 plastic scintillator (Eljen Technology, Sweetwater, TX, USA) were irradiated at the TRIUMF Neutron Facility and the Proton Therapy Research Centre. In the proton beam, we compared the raw Bragg peak and spread-out Bragg peak response to the industry standard Markus chamber detector. Both scintillator sensors exhibited quenching at high LET in the Bragg peak, presenting a peak-to-entrance ratio of 2.59 for the EJ-260 and 2.63 for the SCSF-3HF fibre, compared to 3.70 for the Markus chamber. The SCSF-3HF sensor demonstrated 1.3 times the sensitivity to protons and 3 times the sensitivity to neutrons as compared to the EJ-260 sensor. Combined with our equations relating neutron and proton contributions to dose during proton irradiations, and the application of Birks' quenching correction, these fibres provide valid candidates for inexpensive and replicable proton-neutron discrimination detectors}, language = {en} } @article{LowisFergusonPaulssenetal.2021, author = {Lowis, Carsten and Ferguson, Simon and Paulßen, Elisabeth and Hoehr, Cornelia}, title = {Improved Sc-44 production in a siphon-style liquid target on a medical cyclotron}, series = {Applied Radiation and Isotopes}, volume = {172}, journal = {Applied Radiation and Isotopes}, number = {Art. 109675}, publisher = {Elsevier}, address = {Amsterdam}, issn = {0969-8043}, doi = {10.1016/j.apradiso.2021.109675}, year = {2021}, language = {en} } @article{MoretAlkemadeUpcraftetal.2020, author = {Moret, J.L.T.M. and Alkemade, J. and Upcraft, T.M. and Paulßen, Elisabeth and Wolterbeek, H.T. and Ommen, J.R. van and Denkova, A.G.}, title = {The application of atomic layer deposition in the production of sorbents for ⁹⁹Mo/⁹⁹ᵐTc generator}, series = {Applied Radiation and Isotopes}, volume = {164}, journal = {Applied Radiation and Isotopes}, number = {109266}, publisher = {Elsevier}, address = {Amsterdam}, issn = {0969-8043}, doi = {10.1016/j.apradiso.2020.109266}, pages = {9}, year = {2020}, abstract = {New production routes for ⁹⁹Mo are steadily gaining importance. However, the obtained specific activity is much lower than currently produced by the fission of U-235. To be able to supply hospitals with ⁹⁹Mo/⁹⁹ᵐTc generators with the desired activity, the adsorption capacity of the column material should be increased. In this paper we have investigated whether the gas phase coating technique Atomic Layer Deposition (ALD), which can deposit ultra-thin layers on high surface area materials, can be used to attain materials with high adsorption capacity for ⁹⁹Mo. For this purpose, ALD was applied on a silica-core sorbent material to coat it with a thin layer of alumina. This sorbent material shows to have a maximum adsorption capacity of 120 mg/g and has a ⁹⁹ᵐTc elution efficiency of 55 ± 2\% based on 3 executive elutions.}, language = {en} } @article{deBloisdeZangerPaulssenetal.2018, author = {de Blois, Eric and de Zanger, Rory M. S. and Paulßen, Elisabeth and Sze Chan, Ho and Breeman, Wouter A. P.}, title = {Semi-automated system for concentrating 68Ga-eluate to obtain high molar and volume concentration of 68Ga-Radiopharmaca for preclinical applications}, series = {Nuclear Medicine and Biology}, volume = {64-65}, journal = {Nuclear Medicine and Biology}, publisher = {Elsevier}, address = {Amsterdam}, doi = {10.1016/j.nucmedbio.2018.06.006}, pages = {16 -- 21}, year = {2018}, abstract = {68Ga-radiopharmaceuticals are common in the field of Nuclear Medicine to visualize receptor-mediated processes. In contrast to straightforward labeling procedures for clinical applications, preclinical in vitro and in vivo applications are hampered for reasons like e.g. volume restriction, activity concentration, molar activity and osmolality. Therefore, we developed a semiautomatic system specifically to overcome these problems. A difficulty appeared unexpectedly, as intrinsic trace metals derived from eluate (Zn, Fe and Cu) are concentrated as well in amounts that influence radiochemical yield and thus lower molar activity.}, language = {en} } @article{LiuSchaapBallemansetal.2017, author = {Liu, Z. and Schaap, K. S. and Ballemans, L. and de Blois, E. and Rohde, M. and Paulßen, Elisabeth}, title = {Measurement of reaction kinetics of [177Lu]Lu-DOTA-TATE using a microfluidic system}, series = {Dalton Transactions}, volume = {46}, journal = {Dalton Transactions}, number = {42}, issn = {1477-9234}, doi = {10.1039/C7DT01830D}, pages = {14669 -- 14676}, year = {2017}, language = {en} } @article{PaulssenLengkeekLeetal.2016, author = {Paulßen, Elisabeth and Lengkeek, Nigel A. and Le, Van So and Pellegrini, Paul A. and Greguric, Ivan and Weiner, Ron}, title = {The role of additives in moderating the influence of Fe(III) and Cu(II) on the radiochemical yield of [⁶⁸Ga(DOTATATE)]}, series = {Applied Radiation and Isotopes}, volume = {107}, journal = {Applied Radiation and Isotopes}, publisher = {Elsevier}, address = {Amsterdam}, issn = {1872-9800}, doi = {10.1016/j.apradiso.2015.09.008}, pages = {13 -- 16}, year = {2016}, abstract = {[⁶⁸Ga(DOTATATE)] has demonstrated its clinical usefulness. Both Fe³⁺ and Cu²⁺, potential contaminants in Gallium-68 generator eluent, substantially reduce the radiochemical (RC) yield of [⁶⁸Ga(DOTATATE)] if the metal/ligand ratio of 1:1 is exceeded. A variety of compounds were examined for their potential ability to reduce this effect. Most had no effect on RC yield. However, addition of phosphate diminished the influence of Fe³⁺ by likely forming an insoluble iron salt. Addition of ascorbic acid reduced Cu²⁺ and Fe³⁺ to Cu⁺ and Fe²⁺ respectively, both of which have limited impact on RC yields. At low ligand amounts (5 nmol DOTATATE), the addition of 30 nmol phosphate (0.19 mM) increased the tolerance of Fe3⁺ from 4 nmol to 10 nmol (0.06 mM), while the addition of ascorbic acid allowed high RC yields (>95\%) in the presence of 40 nmol Fe³⁺ (0.25 mM) and 100 nmol Cu²⁺ (0.63 mM). The effect of ascorbic acid was highly pH-dependant, and gave optimal results at pH 3.}, language = {en} } @article{InfantinoPaulssenMostaccietal.2016, author = {Infantino, Angelo and Paulßen, Elisabeth and Mostacci, Domiziano and Schaffer, Paul and Trinczek, Michael and Hoehr, Cornelia}, title = {Assessment of the production of medical isotopes using the Monte Carlo code FLUKA: Simulations against experimental measurements}, series = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, volume = {366}, journal = {Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms}, publisher = {Elsevier}, address = {Amsterdam}, issn = {1872-9584}, doi = {10.1016/j.nimb.2015.10.067}, pages = {117 -- 123}, year = {2016}, abstract = {The Monte Carlo code FLUKA is used to simulate the production of a number of positron emitting radionuclides, ¹⁸F, ¹³N, ⁹⁴Tc, ⁴⁴Sc, ⁶⁸Ga, ⁸⁶Y, ⁸⁹Zr, ⁵²Mn, ⁶¹Cu and ⁵⁵Co, on a small medical cyclotron with a proton beam energy of 13 MeV. Experimental data collected at the TR13 cyclotron at TRIUMF agree within a factor of 0.6 ± 0.4 with the directly simulated data, except for the production of ⁵⁵Co, where the simulation underestimates the experiment by a factor of 3.4 ± 0.4. The experimental data also agree within a factor of 0.8 ± 0.6 with the convolution of simulated proton fluence and cross sections from literature. Overall, this confirms the applicability of FLUKA to simulate radionuclide production at 13 MeV proton beam energy.}, language = {en} } @article{PaulssenHoehrHouetal.2015, author = {Paulßen, Elisabeth and Hoehr, Cornelia and Hou, Xinchi and Hanemaayer, Victoire and Zeisler, Stefan and Adam, Michael J. and Ruth, Thomas J. and Celler, Anna and Buckley, Ken and Benard, Francois and Schaffer, Paul}, title = {Production of Y-86 and other radiometals for research purposes using a solution target system}, series = {Nuclear medicine and biology}, volume = {42}, journal = {Nuclear medicine and biology}, number = {11}, publisher = {Elsevier}, address = {Amsterdam}, issn = {1872-9614}, doi = {10.1016/j.nucmedbio.2015.06.005}, pages = {842 -- 849}, year = {2015}, language = {en} }