Irradiation tests on PHWR type fuel elements in TRIGA research reactor of INR Pitesti
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G. Horhoianu
Abstract
Nine PHWR type fuel elements with reduced length were irradiated in loop A of the TRIGA Research Reactor of INR Pitesti. The primary objective of the test was to determine the performance of nuclear fuel fabricated at INR Pitesti at high linear powers in pressurized water conditions. Six fuel elements were irradiated with a ramp power history, achieving a maximum power of 45 kW/m during pre-ramp and of 64 kW/m in the ramp. The maximum discharge burnup was of 216 MWh/kgU. Another three fuel elements with reduced length were irradiated with declining power history. At the beginning of irradiation the fuel elements achieved a maximum linear power of 66 kW/m. The maximum fuel power was about 1.3 times the maximum expected in PHWR. The maximum discharge burnup was 205 MWh/kgU. The elements were destructively examined in the hot cells of INR Pitesti. Temperature-sensitive parameters such as UO2 grain growth, fission-gas release and sheath deformations were examined. The tests proved the feasibility of irradiating PHWR type fuel elements at linear powers up to 66 kW/m under pressurized water conditions and demonstrated the possibility of more flexible operation of this fuel in power reactors. This paper presents the results of the investigation.
Kurzfassung
Im Loop A des TRIGA Forschungsreaktors des INR Pitesti wurden 9 Schwerwasser-Druckreaktor-Brennelemente mit verkürzter Länge untersucht. Ziel dieser Untersuchungen war die Bestimmung der Qualität des im INR Pitesti hergestellten Brennstoffs bei hohen linearen Bestrahlungsrampen unter Druckwasserbedingungen. Dabei wurden 6 Brennelemente einer ansteigenden und drei Brennelemente einer abnehmenden Bestrahlungsrampe ausgesetzt. Die maximale Bestrahlungsleistung betrug das 1,3 fache der erwarteten maximalen Bestrahlungsleistung in einem schwerwassermoderierten Druckreaktor. Der maximale Abbrand der getesteten Brennelemente betrug 205 MWh/kgU. Die derart bestrahlten Brennelementproben wurden anschließend zerstörend geprüft in den heißen Zellen des INR Pitesti. Dabei wurden u.a. temperatur-sensitive Parameter wie die UO2-Korngröße, die Spaltgasfreisetzung und die Deformation der Hülle untersucht. Die Ergebnisse werden im vorliegenden Beitrag vorgestellt und zeigen, dass der im INR Pitesti hergestellte Brennstoff eine flexiblere Betriebsweise in den Reaktoren ermöglicht.
References
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© 2012, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Remarks on boiling water reactor stability analysis – part 2: stability monitoring
- Irradiation tests on PHWR type fuel elements in TRIGA research reactor of INR Pitesti
- Heat transfer study of a submerged reactor channel under boil-off condition
- Dynamic assessment for life extension of nuclear power plants (NPPs) using system dynamics (SD) method
- Effect of using FLiBe and FLiNaBe molten salts bearing plutonium fluorides on the neutronic performance of PACER
- Evaluations of the CCFL and critical flow models in TRACE for PWR LBLOCA analysis
- Development of program DETSIM to simulate detector's full energy peak efficiency
- The criticality calculations for one-speed neutrons in a reflected slab with anisotropic scattering using the modified UN method
- A detailed investigation of interactions within the shielding to HPGe detector response using MCNP code
- Cosmic ray angular distribution employing plastic scintillation detectors and flash-ADC/FPGA-based readout systems
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Remarks on boiling water reactor stability analysis – part 2: stability monitoring
- Irradiation tests on PHWR type fuel elements in TRIGA research reactor of INR Pitesti
- Heat transfer study of a submerged reactor channel under boil-off condition
- Dynamic assessment for life extension of nuclear power plants (NPPs) using system dynamics (SD) method
- Effect of using FLiBe and FLiNaBe molten salts bearing plutonium fluorides on the neutronic performance of PACER
- Evaluations of the CCFL and critical flow models in TRACE for PWR LBLOCA analysis
- Development of program DETSIM to simulate detector's full energy peak efficiency
- The criticality calculations for one-speed neutrons in a reflected slab with anisotropic scattering using the modified UN method
- A detailed investigation of interactions within the shielding to HPGe detector response using MCNP code
- Cosmic ray angular distribution employing plastic scintillation detectors and flash-ADC/FPGA-based readout systems
