Determination of 89Zr production parameters via different reactions using ALICE and TALYS codes
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M. Taghilo
Abstract
89Zr is an important positron-emitting radionuclide for positron emission tomography (PET) and used in the field of tumor diagnostics, tumor therapy and the investigation of the bio-kinetic. The ALICE-91 and TALYS-1.0 codes were used to calculate excitation function for proton, alpha, deuteron and neutron induced on various targets that lead to the production of 89Zr radioisotopes using intermediate energy accelerators. Requisite thickness of the targets was obtained by SRIM code. The 89Zr production yield was evaluated using excitation function and stopping power. For the 89Y(p, n)89Zr reaction, the calculation data were compared with the experimental data. The 89Y(p, n)89Zr process was determined as most interesting one due to radionuclide purity. The ALICE-91 and TALYS-1.0 codes predict a maximum cross-section of about 939.86 mb at 15MeV and 860 mb at 13MeV respectively for this reaction.
Kurzfassung
89Zr ist ein wichtiges Positronen-emittierendes Radionuklid für die Positronenemissionstomographie (PET) und wird auf dem Gebiet der Tumordiagnostik, der Tumortherapie und biokinetischer Untersuchungen verwendet. Die Codes ALICE-91 and TALYS-1.0 wurden verwendet zur Berechnung der Anregungsfunktionen von Protonen, Alphateilchen, Deuteronen und Neutronen zur Erzeugung von 89Zr mit Hilfe von Beschleunigern. Die erforderliche Dicke der Targets wurde mit Hilfe des SRIM Codes bestimmt. Die 89Zr Ausbeute wurde bewertet mit Hilfe der Anregungsfunktion und Bremsvermögens. Für die 89Y(p, n)89Zr Reaktion wurden die berechneten Daten verglichen mit experimentellen Ergebnissen. Die 89Y(p, n)89Zr Reaktion stellte sich wegen der Radionuklidreinheit als besonders interessant heraus. Mit Hilfe der Codes ALICE-91 und TALYS-1.0 wurde ein maximaler Wirkungsquerschnitt von 939,86 mb bei 15MeV und 860 mb bei 13MeV für diese Reaktion bestimmt.
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© 2011, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Overview of safety improvement during RBMK-1500 reactor core lifetime upgrading
- Strategy, main stages and progress of the Ignalina Nuclear Power Plant decommissioning
- Environmental safety aspects of the new solid radioactive waste management and storage facility at the Ignalina Nuclear Power Plant
- Preliminary evaluation of effect of Engineered Safety Features on source term for AHWR containment
- Burn up extension in a PBMR-400 full core using weapon grade plutonium fuel mixed with thorium
- A study on the damage of potential first wall materials in a nuclear fusion reactor using plutonium bearing salt
- An analytical benchmark of MYRRHA ADS in cylindrical geometry
- Dosimetric characteristics of three new design 125I brachytherapy sources
- Determination of 89Zr production parameters via different reactions using ALICE and TALYS codes
- Novel dose calculation and characterization of 32P intravascular brachytherapy stent source
- Cyclotron production of 85Sr by proton irradiation of natRb
- Lessons learnt from PSA for new and advanced reactors in Russia
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Overview of safety improvement during RBMK-1500 reactor core lifetime upgrading
- Strategy, main stages and progress of the Ignalina Nuclear Power Plant decommissioning
- Environmental safety aspects of the new solid radioactive waste management and storage facility at the Ignalina Nuclear Power Plant
- Preliminary evaluation of effect of Engineered Safety Features on source term for AHWR containment
- Burn up extension in a PBMR-400 full core using weapon grade plutonium fuel mixed with thorium
- A study on the damage of potential first wall materials in a nuclear fusion reactor using plutonium bearing salt
- An analytical benchmark of MYRRHA ADS in cylindrical geometry
- Dosimetric characteristics of three new design 125I brachytherapy sources
- Determination of 89Zr production parameters via different reactions using ALICE and TALYS codes
- Novel dose calculation and characterization of 32P intravascular brachytherapy stent source
- Cyclotron production of 85Sr by proton irradiation of natRb
- Lessons learnt from PSA for new and advanced reactors in Russia
