1. Nuclear Safety Research Unit FRAPCON/FRAPTRAN users group meting Manchester (UK), 07.09.12 CIEMAT ACTIVITIES on FRAPCON/FRAPTRAN APPLICATIONS (2010-2012)

2. Nuclear Safety Research Unit FRAPCON/FRAPTRAN users group meting Manchester (UK), 07.09.12 PROJECTS TERMOMEC (Thermo-mechanical Behaviour of Nuclear Fuel at High Burnup) AICAST (Analysis of Integrity of Spent Fuel in Dry Storage and Transport)  Sponsor: CSN (Spanish Nuclear Regulatory Body)  Codes used: FRAPCON-3.4 and FRAPTRAN-1.4  Sponsor: ENRESA (Spanish Radioactive Waste Management Company)  Code used: FRAPCON-3.4

3. Nuclear Safety Research Unit FRAPCON/FRAPTRAN users group meting Manchester (UK), 07.09.12 FRAPCON-3.4 + FRAPTRAN-1.4 RampsRIA OECD RIA-Benchmark (CABRI, NSRR) TERMOMEC MAIN ACTIVITIES 3 rd SCIP Benchmark (R2, HALDEN) Uncertainties analysis CIP0-1 (deterministic) LOCA HALDEN Other cases (probabilistic)

4. Nuclear Safety Research Unit FRAPCON/FRAPTRAN users group meting Manchester (UK), 07.09.12 AICAST MAIN ACTIVITIES FRAPCON-3.4xt CreepHydrogen Dry storage DHC Hydride radial reorientation (HRR) Embrittlement (HE) StageIIIIII MechanismCreepDHC + HEHRR

5. Nuclear Safety Research Unit FRAPCON/FRAPTRAN users group meting Manchester (UK), 07.09.12 SPECIFIC QUESTIONS Gap from plotter file different from (r clad in - r fuel out ) (values from“print2.f”) Clad thickness: FRAPCON-3.4 FRAPTRAN-1.4 (RIA simulations) If clad failure →  ztot ≠  ztherm +  zelast +  zperm T clad out with oxide ≈ T clad out without oxide (completely spalled)  tcc in “frpcon.f” axially changes (clad thinning due to oxide)  tcc in “print2.f” does NOT change from node to node (top value) → same r clad out  Transmitted to “ccreep.f” → stress not affected by axial variation

6. Nuclear Safety Research Unit FRAPCON/FRAPTRAN users group meting Manchester (UK), 07.09.12 RELATED PAPERS L.E. Herranz, I. Vallejo, G. Khvostov, J. Sercombe, G. Zhou “Assessment of fuel rod performance codes under ramp scenarios investigated within the SCIP project”, Nuclear Engineering and Design 241 (2011), 815-825 A. Hughet, I. Vallejo, L.E. Herranz, “Pretest modeling of CABRI CIP3-1 test with FRAPCON-3/FRAPTRAN Codes”, 2011 Water Reactor Fuel Performance Meeting Chengdu, China, Sept. 11-14, 2011 A. Hughet, L.E. Herranz, “ASSESSMENT OF STEADY STATE UNCERTAINTIES IMPACT ON RIA MODELING”, IAEA Technical Meeting on Fuel Behavior under Transient and LOCA Mito city, Ibaraki- ken, 19-21 October 2011 I. Sagrado, I. Vallejo, L.E. Herranz, “Analysis of CIP0-1 and CIP3-1 tests with FRAPTRAN and SCANAIR: effect of the major codes assumptions”, Top Fuel 2012 F. Feria, L. Herranz, “FRAPCON-3.4 extension to model hydrogen effects on cladding mechanical behavior during dry storage”, Top Fuel 2012 F. Feria, L. Herranz, “Creep assessment of Zry-4 cladded high burnup fuel under dry storage”, Progress in Nuclear Energy, Vol 53, p 395-400, 2011 L. Herranz, F. Feria “Extension of the FRAPCON-3.3 creep model to dry storage conditions”, Progress in Nuclear Energy, Vol 52, p 634-639, 2010 F. Feria, L. Herranz, “Evaluation of creep during dry storage in low and high burnup fuels”, IAEA International Conference on Management of Spent Fuel from Nuclear Power Reactors, Vienna, 2010 + 5 technical reports

7. Nuclear Safety Research Unit FRAPCON/FRAPTRAN users group meting Manchester (UK), 07.09.12 THANK YOU FOR YOUR ATTENTION

8. Nuclear Safety Research Unit FRAPCON/FRAPTRAN users group meting Manchester (UK), 07.09.12 Oxide from FRAPCON-3.4 (restart)No oxide (set to “0” restart) Changes in outside clad T very small (0-17 ºC) Changes in outside clad T very small (0-17 ºC) Similar behavior in other cases (CIP0-1…) Similar behavior in other cases (CIP0-1…) Oxide  [75-100]  m  T Ox max  391ºC (ouput file) SPECIFIC QUESTIONS. FRAPTRAN-1.4 CIP3-1

9. Nuclear Safety Research Unit FRAPCON/FRAPTRAN users group meting Manchester (UK), 07.09.12 SPECIFIC QUESTIONS. FRAPTRAN-1.4 CIP3-1