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Nuclear Safety Research Unit Vienna (Austria), 31.05-4.06.2010 IAEA meeting Evaluation of creep during dry storage in low and high burnup fuels F. Feria,

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Presentation on theme: "Nuclear Safety Research Unit Vienna (Austria), 31.05-4.06.2010 IAEA meeting Evaluation of creep during dry storage in low and high burnup fuels F. Feria,"— Presentation transcript:

1 Nuclear Safety Research Unit Vienna (Austria), 31.05-4.06.2010 IAEA meeting Evaluation of creep during dry storage in low and high burnup fuels F. Feria, L.E. Herranz CONTENTS 1.Motivation and objective 2.Extension of FRAPCON-3.3 creep law 3.Creep assessment 4.Final remarks

2 Nuclear Safety Research Unit Vienna (Austria), 31.05-4.06.2010 IAEA meeting 1. MOTIVATION AND OBJECTIVE Safety objectives: -Radiation dose -Subcriticality -Confinement -Retrievability Degrading mechanisms SCC Creep DHC Cladding integrity Evaluation in low and high burnup

3 Nuclear Safety Research Unit Vienna (Austria), 31.05-4.06.2010 IAEA meeting In-FRAPCON modelling 2. EXTENSION OF FRAPCON-3.3 CREEP LAW Creep law:

4 Nuclear Safety Research Unit Vienna (Austria), 31.05-4.06.2010 IAEA meeting 2. EXTENSION OF FRAPCON-3.3 CREEP LAW Creep law validity range Restricted to in-reactor conditions Extension of the creep law is needed to apply the code to dry storage conditions

5 Nuclear Safety Research Unit Vienna (Austria), 31.05-4.06.2010 IAEA meeting Zircaloy-4 database (EDF) 2. EXTENSION OF FRAPCON-3.3 CREEP LAW Generic correlation

6 Nuclear Safety Research Unit Vienna (Austria), 31.05-4.06.2010 IAEA meeting CIEMAT creep law 2. EXTENSION OF FRAPCON-3.3 CREEP LAW

7 Nuclear Safety Research Unit Vienna (Austria), 31.05-4.06.2010 IAEA meeting CIEMAT creep law 2. EXTENSION OF FRAPCON-3.3 CREEP LAW

8 Nuclear Safety Research Unit Vienna (Austria), 31.05-4.06.2010 IAEA meeting Implementation   ≥ 121 MPa → Creep law parameters derived from irradiated claddings data   ≤ 121 MPa → Creep law parameters derived from non-irradiated claddings data 2. EXTENSION OF FRAPCON-3.3 CREEP LAW Together with a suitable logic that allows choosing between the “in-reactor” equation and the dry storage equation, according to the prevailing conditions at the calculation time The extension splits in two hoop stress ranges: No experimental data is available with irradiated material under low hoop stress

9 Nuclear Safety Research Unit Vienna (Austria), 31.05-4.06.2010 IAEA meeting 3. CREEP ASSESMENT a) Zircaloy-4 45 GWd/tU 1º) In-reactor irradiation 2º) Pool storage (1 year) 3º) Dry out (1 day) 4º) Dry storage (2 years) Phases b) Zircaloy-4 63 GWd/tU Postulated scenarios

10 Nuclear Safety Research Unit Vienna (Austria), 31.05-4.06.2010 IAEA meeting 3. CREEP ASSESMENT Results a) Zircaloy-4 45 GWd/tU b) Zircaloy-4 63 GWd/tU Once dry storage starts hoop stress causes a creep-out situation

11 Nuclear Safety Research Unit Vienna (Austria), 31.05-4.06.2010 IAEA meeting The creep main impact would take place during the first months 3. CREEP ASSESMENT Results In no case creep reaches 1 % strain limit Nearly 4 times higher hoop strain as burn-up is increased by 40 %

12 Nuclear Safety Research Unit Vienna (Austria), 31.05-4.06.2010 IAEA meeting 4. FINAL REMARKS High burn-up effect seems substantial and causes major differences in the nuclear fuel response in terms of creep Further work: Extend CIEMAT creep law to irradiated fuel rods submitted to low stresses Extend the study up to 100 years to estimate the final creep asymptotic value The results would have a conservative nature because the irradiation hardening effect is not considered at low stresses

13 Nuclear Safety Research Unit Vienna (Austria), 31.05-4.06.2010 IAEA meeting ACKNOWLEDGMENTS The authors are indebted to ENRESA for their financial support and the technical discussions held and to the FRAPCON-3 developers for their technical support during this work

14 Nuclear Safety Research Unit Vienna (Austria), 31.05-4.06.2010 IAEA meeting THANK YOU FOR YOUR ATTENTION

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