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Prediction of 67Ga production using the Monte Carlo code MCNPX
Prediction of 67Ga production using the Monte Carlo code MCNPX
- Source :
- Applied Radiation and Isotopes. 77:14-17
- Publication Year :
- 2013
- Publisher :
- Elsevier BV, 2013.
-
Abstract
- The widely used Monte Carlo simulation code Monte Carlo N-Particle System (MCNPX) has been utilized to simulate the production of 67Gallium via multiple nuclear reaction channels. Based on the MCNPX-generated, energy-dependent proton flux within a Zn target during irradiation, the 67Ga production yield was determined. Theoretical calculations of the production yield using the stopping power from the SRIM (stopping and range of ions in matter) code were compared to the measurements from the MCNPX code. These results were in good agreement with reported data, thus confirming the usefulness and accuracy of MCNPX as a tool for the design and optimization of targets for the production of other radionuclides.
- Subjects :
- Physics
Nuclear reaction
Range (particle radiation)
Models, Statistical
Radiation
Nuclear engineering
Physics::Medical Physics
Monte Carlo method
Radiochemistry
Gallium Radioisotopes
Proton flux
Models, Chemical
Monte carlo code
Isotope Labeling
Yield (chemistry)
Materials Testing
Stopping power (particle radiation)
Production (economics)
Computer Simulation
Radiometry
Nuclear Experiment
Monte Carlo Method
Software
Subjects
Details
- ISSN :
- 09698043
- Volume :
- 77
- Database :
- OpenAIRE
- Journal :
- Applied Radiation and Isotopes
- Accession number :
- edsair.doi.dedup.....457af50bceaeb4bd331817b1e20e90c6
- Full Text :
- https://doi.org/10.1016/j.apradiso.2013.02.001