In-pile measurements of the fission gas pressure and comparison with ROFEM code results
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G. Horhoianu
Abstract
Two experimental fuel elements with different UO2 grain size were irradiated in the C2 capsule in the TRIGA MT reactor of INR Pitesti to a burn-up of 178.9 MWh kg−1 U and linear powers between 45 to 60 kW m−1. Both elements were instrumented to measure internal gas pressure during irradiation. Experimental results presented in this paper represent data relative to two fuel elements with different UO2 grain size. The predictions of fuel performance code ROFEM in terms of internal gas pressure were compared with the experimental data. Experimental programs are in progress at INR Pitesti. New instrumented tests are planed to be performed in the C2 capsule in order to establish the pellet microstructure influence on fission gas release. This paper describes measuring techniques used at INR Pitesti and present experimental results of the in-pile tests comparatively with the ROFEM code predictions.
Kurzfassung
Zwei experimentelle Brennelemente mit verschiedenen UO2 Korngrößen wurden in der C2 Kapsel im TRIGA MT Reaktor des INR Pitesti bestrahlt bis zu einem Abbrand von 178.9 MWh kg−1 U und linearen Leistungen zwischen 45 und 60 kW m−1. Beide Elemente waren während der Bestrahlung für die Messung des inneren Gasdruckes instrumentiert. Die in diesem Beitrag vorgestellten experimentellen Ergebnisse zeigen Daten aus zwei Brennelementen mit unterschiedlichen UO2 Korngrößen. Die Vorhersagen des Brennstoffverhaltens mit Hilfe des ROFEM Codes in Form des inneren Gasdruckes wurden verglichen mit den experimentellen Daten. Weitere experimentelle Programme sind am INR Pitesti im Gange. Die Durchführung neu ausgelegter Testverfahren in der C2 Kapsel zur Bestimmung des Einflusses der Pellet-Mikrostruktur auf die Spaltgasfreisetzung ist geplant. Diese Arbeit beschreibt die am INR Pitesti verwendeten Messverfahren und stellt experimentelle Ergebnisse von In-Pile Messungen im Vergleich mit ROFEM Code Vorhersagen vor.
References
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© 2010, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Numerical simulation on a HPLWR fuel assembly flow with one revolution of wrapped wire spacers
- Axial-power-shape induced frequency shifts in BWR stability measurements
- Numerical investigation of heat transfer in the vertical annulus between pressure tube and calandria tube of the advanced water cooled reactor
- Uncertainty analysis for fission products transport in CANDU primary heat transport during a severe accident
- Definition of conservative conditions for RIA analysis in the modernized RBMK reactor core
- Assessment of different mechanisms of C-14 production in irradiated graphite of RBMK-1500 reactors
- In-pile measurements of the fission gas pressure and comparison with ROFEM code results
- The time-dependent P1 model for the neutronics of multiplying systems: a review
- Efficiency of reflection coefficients in the isotropic neutron transport equation and computation of the critical-half thicknesses
- Finite differences with exponential filtering in the calculation of reactivity
- Asymptotic solution of critical thickness with direct second kind Chebyshev polynomial approximation in forward and backward scattering
- Interactions of radionuclides in solution with ions and with trace concentrations of solid phase
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Numerical simulation on a HPLWR fuel assembly flow with one revolution of wrapped wire spacers
- Axial-power-shape induced frequency shifts in BWR stability measurements
- Numerical investigation of heat transfer in the vertical annulus between pressure tube and calandria tube of the advanced water cooled reactor
- Uncertainty analysis for fission products transport in CANDU primary heat transport during a severe accident
- Definition of conservative conditions for RIA analysis in the modernized RBMK reactor core
- Assessment of different mechanisms of C-14 production in irradiated graphite of RBMK-1500 reactors
- In-pile measurements of the fission gas pressure and comparison with ROFEM code results
- The time-dependent P1 model for the neutronics of multiplying systems: a review
- Efficiency of reflection coefficients in the isotropic neutron transport equation and computation of the critical-half thicknesses
- Finite differences with exponential filtering in the calculation of reactivity
- Asymptotic solution of critical thickness with direct second kind Chebyshev polynomial approximation in forward and backward scattering
- Interactions of radionuclides in solution with ions and with trace concentrations of solid phase
