Optimization and analysis of the effects of physical parameters in a TRIGA-ADSR
Abstract
In the current research, sensitivity analysis of the accelerator and fissionable and non-fissionable spallation targets containing U-238, Pb, LBE and W materials, Yn/p (spallation neutron yield), Ep (proton energy), G (energy gain), ϕ* (importance of neutron source), Keff (effective multiplication coefficient), Ks (source multiplication coefficient) and Ip (accelerator current) for two cases of Ks including: 0.91 and 0.97 in an Accelerator Driven Subcritical Reactor TRIGA (TRIGA-ADSR) were studied. These neutronic factors were computed by MCNPX code. The obtained results of this study show that for the Yn/p and G parameters, there is an optimum energy from 800 to 1000 MeV. Furthermore, according to the results, if this reactor would be operated close to criticality, the effect of reactivity insertion on the core power is raised. Also, the optimum value of Ks = 0.97 was chosen as adequate multiplication coefficient in this research because of appropriate margins. Lastly, the results of these investigations show that analysis of sensitivity and specificity of the accelerator and spallation target factors is required to optimize the neutronic plan of ADSR.
Kurzfassung
Im vorliegenden Beitrag wurde eine Sensitivitätsanalyse des Beschleunigers durchgeführt und spaltbare und nicht spaltbare Spallationstargets mit U-238, Pb, LBE und W Materialien, Yn/p (Spallationsneutronenausbeute), Ep (Protonenenergie), G (Energiegewinn), ϕ* (Bedeutung der Neutronenquelle), Keff (effectiver Multiplikationskoeffizient), Ks (Quellen-bezogener Multiplikationskoeffizient) und Ip (Beschleunigerstrom) für zwei Fälle von Ks mit 0.91 und 0.97 in Beschleuniger-betriebenen unterkritischen TRIGA Reaktor (TRIGA-ADSR) untersucht. Die neutronenphysikalischen Eigenschaften wurden mit Hilfe des MCNPX-Codes berechnet. Die Ergebnisse zeigen, dass es für die Parameter Yn/p and G eine optimale Energie zwischen 800 und 1000 MeV gibt. Würde man den Reaktor nahe der Kritikalitätsgrenze betreiben, würde sich die Frage des Einflusses der Reaktivitätszufuhr auf die Kernleistung stellen. Der optimale Wert von Ks = 0.97 wurde als geeigneter Multiplikationskoeffizient gewählt. Die Ergebnisse der Untersuchungen zeigen, dass die Analyse der Sensitivität und der Spezifizität des Beschleunigers und der Faktoren der Spallationstargets erforderlich ist um die neutronenphysikalischen Eigenschaften des ADSR zu optimieren.
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© 2017, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- SIMULATE-3 K coupled code applications
- Application of the new IAPWS Guideline on the fast and accurate calculation of steam and water properties with the Spline-Based Table Look-Up Method (SBTL) in RELAP-7
- Simulation of water hammer phenomena using the system code ATHLET
- New version of the reactor dynamics code DYN3D for Sodium cooled Fast Reactor analyses
- Sensitivity analysis for thermo-hydraulics model of a Westinghouse type PWR: verification of the simulation results
- Calculation of the fuel temperature coefficient of reactivity considering non-uniform radial temperature distribution in the fuel rod
- The effect of boron dilution transient on the VVER-1000 reactor core using MCNP and COBRA-EN codes
- Modelling of the spent fuel heat-up in the spent fuel pools using one-dimensional system codes and CFD codes
- Optimization and analysis of the effects of physical parameters in a TRIGA-ADSR
- A comparison study for mass attenuation coefficients of some amino acids using MCNP code
- Validation of radioactive isotope activity measurement in homogeneous waste drum using Monte Carlo codes
- Study of the response reduction of LiF:Mg, Ti dosimeter for high dose dosimetry
- Non-contact micro mass evaluation method using an X-ray microscope
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- SIMULATE-3 K coupled code applications
- Application of the new IAPWS Guideline on the fast and accurate calculation of steam and water properties with the Spline-Based Table Look-Up Method (SBTL) in RELAP-7
- Simulation of water hammer phenomena using the system code ATHLET
- New version of the reactor dynamics code DYN3D for Sodium cooled Fast Reactor analyses
- Sensitivity analysis for thermo-hydraulics model of a Westinghouse type PWR: verification of the simulation results
- Calculation of the fuel temperature coefficient of reactivity considering non-uniform radial temperature distribution in the fuel rod
- The effect of boron dilution transient on the VVER-1000 reactor core using MCNP and COBRA-EN codes
- Modelling of the spent fuel heat-up in the spent fuel pools using one-dimensional system codes and CFD codes
- Optimization and analysis of the effects of physical parameters in a TRIGA-ADSR
- A comparison study for mass attenuation coefficients of some amino acids using MCNP code
- Validation of radioactive isotope activity measurement in homogeneous waste drum using Monte Carlo codes
- Study of the response reduction of LiF:Mg, Ti dosimeter for high dose dosimetry
- Non-contact micro mass evaluation method using an X-ray microscope
