Investigations on fuel behaviour are carried out in close connection with experimental research, operation feedback and computational analyses. In this framework, OECD/NEA sets up the “public domain database on nuclear fuel performance experiments for the purpose of code development and validation – International Fuel Performance Experiments database”. This database includes: Super-Ramp Project (BWR and PWR), BWR Inter-Ramp Project and CNEA MOX Experiment. The common objectives of these experimental programmes are to investigate the Pellet Cladding Interaction (PCI) failure mechanism and associated phenomena during power ramp tests with the aim to establish LWR fuel failure-safe operating limits. The fuel type comprises PWR, BWR and MOX designs. The burn-up ranges from zero to 44 MWd/kgU. The analyses are carried out in the frame of the IAEA-CRP FUMEX-III. The objective of the activity is to provide an overview of the TRANSURANUS code capabilities in simulating the PCI phenomenon with particular reference to the predictability of the cladding failure. The analysis summarizes the main results achieved after the simulations of the above mentioned databases that include a representative amount of fuel rods (74) of various types and design. The different irradiation histories and burn-ups are accounted for. Focus is given on the main variables, which are involved or may influence the cladding failure and characterize the power ramp tests.

Modeling and Assessment of PCI in LWR Fuel

LUZZI, LELIO
2015-01-01

Abstract

Investigations on fuel behaviour are carried out in close connection with experimental research, operation feedback and computational analyses. In this framework, OECD/NEA sets up the “public domain database on nuclear fuel performance experiments for the purpose of code development and validation – International Fuel Performance Experiments database”. This database includes: Super-Ramp Project (BWR and PWR), BWR Inter-Ramp Project and CNEA MOX Experiment. The common objectives of these experimental programmes are to investigate the Pellet Cladding Interaction (PCI) failure mechanism and associated phenomena during power ramp tests with the aim to establish LWR fuel failure-safe operating limits. The fuel type comprises PWR, BWR and MOX designs. The burn-up ranges from zero to 44 MWd/kgU. The analyses are carried out in the frame of the IAEA-CRP FUMEX-III. The objective of the activity is to provide an overview of the TRANSURANUS code capabilities in simulating the PCI phenomenon with particular reference to the predictability of the cladding failure. The analysis summarizes the main results achieved after the simulations of the above mentioned databases that include a representative amount of fuel rods (74) of various types and design. The different irradiation histories and burn-ups are accounted for. Focus is given on the main variables, which are involved or may influence the cladding failure and characterize the power ramp tests.
2015
Proceedings of the 24th International Conference Nuclear Energy for New Europe
File in questo prodotto:
File Dimensione Formato  
NENE_2015_Portoroz_Slovenia_September_14-17_2015_Paper_811.pdf

Accesso riservato

Descrizione: Articolo principale
: Post-Print (DRAFT o Author’s Accepted Manuscript-AAM)
Dimensione 498.91 kB
Formato Adobe PDF
498.91 kB Adobe PDF   Visualizza/Apri

I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.

Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11311/981582
Citazioni
  • ???jsp.display-item.citation.pmc??? ND
  • Scopus ND
  • ???jsp.display-item.citation.isi??? 0
social impact