Irradiation damages in tantalum spallation target
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C. Villagrasa-Roussel
Abstract
The irradiation by a high intensity proton beam of the spallation target in Accelerator Driven Systems (ADS) gives rise to structural damages that must be considered in the design and handling of such materials. In this work, some of these damages are evaluated in the case of the irradiation of a tantalum target. Tantalum was recently proposed as solid target in the case of low power systems. Unfortunately, not enough experimental data of spallation reactions in this material are available. Therefore, our calculations were made using MCNPX and the stand-alone version of the spallation codes INCL4+ABLA. Results of this work are the concentrations of spallation residues produced in the target after one year of irradiation and calculations of the activity derived. Also displacements per atom in the target material have been evaluated. Different components (elastic scattering and non-elastic reactions) of the displacement cross-sections were calculated with two different methods.
Kurzfassung
Die Bestrahlung eines Spallationstargets in einem Beschleuniger-getriebenen System (ADS) mit einem Protonenstrahl hoher Intensität führt zu Strukturschäden welche beim Entwurf und bei der Handhabe berücksichtigt werden müssen. In der vorliegende Arbeit werden einige dieser Schäden untersucht für den Fall einer Bestrahlung eines Targets aus Tantal. Tantal war vor einigen Jahren vorgeschlagen worden als Feststoff Target in ADS mit niedriger Leistung. Leider sind für dieses Material nur ungenügende experimentelle Daten verfügbar. Deshalb wurden Simulationsrechnungen durchgeführt mit dem Monte Carlo Code MCNPX und mit der Stand-alone Version des Spallations-Codes INCL4+ABLA. Die Ergebnisse dieser Untersuchungen sind die Konzentrationen der Spallationsprodukte nach einem Jahr der Bestrahlung und Berechnung der resultierenden zeitabhängigen Radioaktivität. Weiter wurden „Displacements per Atom“ (DPA) im Targetmaterial ermittelt. Dazu wurden verschiedene Komponenten (elastische Streuung und nicht-elastische Reaktionen) des DPA Querschnitts mit zwei verschiedenen Methoden bestimmt.
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© 2006, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Current use of probabilistic safety evaluations for advanced reactor concepts
- Experiments and comparing calculations on thermohydraulic pressure surges in pipes
- Experimental investigation and CFD simulation of horizontal air/water slug flow
- Uncertainty and sensitivity analysis of the CPS-CC voiding in the RBMK reactor Ignalina-2
- Irradiation damages in tantalum spallation target
- Multigroup neutron reflection and leakage conditions for axial core models with anisotropic scattering
- Performance analyses of the pool-top radiation level reduction systems at the ETRR-2 research reactor
- An interpretation procedure for the purpose of incorporation monitoring during decommissioning of nuclear reactors
- Thermal hydraulics of the fixed bed nuclear reactor concept
- Technical Note
- The critical slab problem for linearly anisotropic scattering and reflecting boundary conditions with the HN method
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Current use of probabilistic safety evaluations for advanced reactor concepts
- Experiments and comparing calculations on thermohydraulic pressure surges in pipes
- Experimental investigation and CFD simulation of horizontal air/water slug flow
- Uncertainty and sensitivity analysis of the CPS-CC voiding in the RBMK reactor Ignalina-2
- Irradiation damages in tantalum spallation target
- Multigroup neutron reflection and leakage conditions for axial core models with anisotropic scattering
- Performance analyses of the pool-top radiation level reduction systems at the ETRR-2 research reactor
- An interpretation procedure for the purpose of incorporation monitoring during decommissioning of nuclear reactors
- Thermal hydraulics of the fixed bed nuclear reactor concept
- Technical Note
- The critical slab problem for linearly anisotropic scattering and reflecting boundary conditions with the HN method
