In this document are reported preliminary results on PDS-XADS fuel rod performance when AISI 316L or T 91 steel as cladding material is adopted. For both options a Transuranus deterministic analysis was performed under Design Basis Conditions - Category I (Normal Operations). A custom version of Transuranus was developed by implementing the main T 91 physical properties. In particular, a cladding swelling and an irradiation creep behaviour, consistent with open literature, have been inserted. Compared to AISI 316L, T 91 cladding improves PDS-XADS fuel rod performance: safety margins on assumed design limits are increased, Fission Gas Release and clad strains are lowered. At End Of Life, a fuel-cladding radial contact is observed in T 91 option, while AISI 316L clad maintains an open-gap fuel rod geometry. This aspect, which is strongly dependent on the assumed fuel and cladding swelling modelling, may play an important role in mitigating the above statements, for this reason further investigations are required.

Preliminary Results on PDS-XADS Fuel Rod Analysis: AISI 316L vs. T 91 Cladding Material

Calabrese, R.
2004-10-13

Abstract

In this document are reported preliminary results on PDS-XADS fuel rod performance when AISI 316L or T 91 steel as cladding material is adopted. For both options a Transuranus deterministic analysis was performed under Design Basis Conditions - Category I (Normal Operations). A custom version of Transuranus was developed by implementing the main T 91 physical properties. In particular, a cladding swelling and an irradiation creep behaviour, consistent with open literature, have been inserted. Compared to AISI 316L, T 91 cladding improves PDS-XADS fuel rod performance: safety margins on assumed design limits are increased, Fission Gas Release and clad strains are lowered. At End Of Life, a fuel-cladding radial contact is observed in T 91 option, while AISI 316L clad maintains an open-gap fuel rod geometry. This aspect, which is strongly dependent on the assumed fuel and cladding swelling modelling, may play an important role in mitigating the above statements, for this reason further investigations are required.
Rapporto tecnico;Reattori sottocritici/ADS;Combustibile nucleare;Termomeccanica
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/7027
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