Capabilities of TRANSURANUS code in simulating power ramp tests from the IFPE database |
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| Authors: | D. Rozzia,M. Adorni,A. Del Nevo,F. D&rsquo Auria |
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| Affiliation: | Gruppo di Ricerca Nucleare San Piero a Grado, DIMNP, Università di Pisa (UNIPI) via Diotisalvi 2, 56100 Pisa, Italy |
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| Abstract: | Investigations of fuel behavior are carried out in close connection with experimental research, operation feedback and computational analyses. OECD NEA sets up the “International Fuel Performance Experiments (IFPE) database”, a public domain database on nuclear fuel performance experiments with the purpose of model development and code validation. The objective of the activity (performed in the framework of the IAEA CRP FUMEX-III project) is to investigate the pellet-clad interaction mechanism and the capability of TRANSURANUS code in simulating the phenomena, processes occurring in the fuel rod during the power ramps, with focus on the parameters influencing the cladding failures. The experimental database adopted is the Studsvik PWR Super-Ramp subprogram, part of the IFPE database, which consists of 28 pressurized water reactor fuel rods power ramped at burnup from 28 to 45 MWd/kgU. Relevant results by TRANSURANUS are presented in connection with the experimental evidences. Focus is given on the PCI/SCC failure, demonstrating that the failure threshold, available in TRANSURANUS, results conservative both in case of KWU and W rods. |
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| Keywords: | AR, after ramp CRP, Coordinate Research Program DIMNP, Dipartimento di Ingegneria Meccanica Nucleare e della Produzione EPRI, Electric Power Research Institute F, failed FGR, fission gas release FRAPCON-3, steady state fuel rod performance code FUMEX, fuel modeling at extended burnup Gd, gadolinium GRNSPG, Gruppo di Ricerca Nucleare San Piero a Grado HBS, high burnup structure IAEA, International Atomic Energy Agency ITU, Institute for Transuranium Elements IFPE, International Fuel Performance JRC, Joint Research Centre KWU/CE, KraftWert Union Combustion Engineering LHR, linear heat rate MATPRO, a library of materials properties library package for light-water-reactor accident analysis NEA, Nuclear Energy Agency NF, non-failed NFF, neutron fast flux OECD, Organization for Economic Co-operation and Development PCI, pellet-clad interaction PTI, prior to irradiation PTR, prior to ramp PWR, pressurized water reactor RTL, ramp terminal level SCC, stress corrosion cracking TU, TRANSURANUS UNIPI, Università di Pisa UO2, uranium oxide Zr-4, Zircaloy-4 W, Westinghouse |
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