TRANSURANUS is a computer program for the thermal and mechanical analysis of fuel rods in nuclear reactors. The TRANSURANUS code consists of a clearly defined mechanical–mathematical framework into which physical models can easily be incorporated. The mechanical–mathematical concept consists of a superposition of a one-dimensional radial and axial description (the so called quasi two-dimensional or 1½-D model). The code was specifically designed for the analysis of a single cylindrical rod. In the current paper, the application of the TRANSURANUS code to the Studsvik BWR Inter-Ramp and PWR Super-Ramp Projects are presented. The activity has been performed in the framework of an agreement between JRC-ITU and the University of Pisa and also of the IAEA FUMEX III project. The objective of the activity is the assessment of the fission gas release model of TRANSURANUS code verison“v1m1j08”, against the above mentioned databases. It constitutes an independent verification of a new model that was implemented at ITU for dealing with release during rapid power changes . The dataset of the BWR Inter-Ramp and PWR Super-Ramp Projects are part of the International Fuel Performance Experiments (IFPE) database. The first addresses the behavior of twenty standard-type unpressurised BWR fuel rods, including preceding base irradiation, during the over-power ramping. Two different values of base irradiations burnup were adopted for the experimental database: about 10 and 20 MWd/kgU. The latter addresses the behavior of twenty-eight light water reactor fuel rods when subject to power ramps (twenty-six are modeled for the current activity), after base irradiation to high burnup (28 to 45 MWd/kgU). Pre-, during-, and post- irradiation, non destructive and destructive examinations were executed, in order to determine and understand the behavior of the fuel rods, but also to provide suitable data, useful for code validation. The experimental data were used for assessing the TRANSURANUS capabilities in predicting the fission gas release. Focus is given on the prediction of the different FGR model options available in the code. The objective of the activity has been fulfilled developing forty-six input decks suitable for the assessment of TRANSURANUS code version “v1m1j08” , . The assessment is focused on fission gas release models available in TRANSURANUS code version “v1m1j08”, with particular emphasis to the new “TFGR model” which is implemented for taking into account the events of rapid power variations. The current paper reports the main outcome of the assessment of the calculations. Conclusive remarks of the activity are provided in the last section.
Capabilities of Transuranus Code in Simulating Power Ramp Tests from the IFPE Database
D'AURIA, FRANCESCO SAVERIO
2009-01-01
Abstract
TRANSURANUS is a computer program for the thermal and mechanical analysis of fuel rods in nuclear reactors. The TRANSURANUS code consists of a clearly defined mechanical–mathematical framework into which physical models can easily be incorporated. The mechanical–mathematical concept consists of a superposition of a one-dimensional radial and axial description (the so called quasi two-dimensional or 1½-D model). The code was specifically designed for the analysis of a single cylindrical rod. In the current paper, the application of the TRANSURANUS code to the Studsvik BWR Inter-Ramp and PWR Super-Ramp Projects are presented. The activity has been performed in the framework of an agreement between JRC-ITU and the University of Pisa and also of the IAEA FUMEX III project. The objective of the activity is the assessment of the fission gas release model of TRANSURANUS code verison“v1m1j08”, against the above mentioned databases. It constitutes an independent verification of a new model that was implemented at ITU for dealing with release during rapid power changes . The dataset of the BWR Inter-Ramp and PWR Super-Ramp Projects are part of the International Fuel Performance Experiments (IFPE) database. The first addresses the behavior of twenty standard-type unpressurised BWR fuel rods, including preceding base irradiation, during the over-power ramping. Two different values of base irradiations burnup were adopted for the experimental database: about 10 and 20 MWd/kgU. The latter addresses the behavior of twenty-eight light water reactor fuel rods when subject to power ramps (twenty-six are modeled for the current activity), after base irradiation to high burnup (28 to 45 MWd/kgU). Pre-, during-, and post- irradiation, non destructive and destructive examinations were executed, in order to determine and understand the behavior of the fuel rods, but also to provide suitable data, useful for code validation. The experimental data were used for assessing the TRANSURANUS capabilities in predicting the fission gas release. Focus is given on the prediction of the different FGR model options available in the code. The objective of the activity has been fulfilled developing forty-six input decks suitable for the assessment of TRANSURANUS code version “v1m1j08” , . The assessment is focused on fission gas release models available in TRANSURANUS code version “v1m1j08”, with particular emphasis to the new “TFGR model” which is implemented for taking into account the events of rapid power variations. The current paper reports the main outcome of the assessment of the calculations. Conclusive remarks of the activity are provided in the last section.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
