Joint Opening Session Margaret McGrath, Halden Project: Welcome and Introduction

Transcription

1 EHPG Sandefjord 2016 Technical Program Fuel and Materials Monday May Joint Opening Session Paper No.: 01 Joint Opening Session Margaret McGrath, Halden Project: Welcome and Introduction Session Chair: Masaaki Ozawa (NRA) William D. Magwood, IV, D-G, OECD NEA: Looking Forward: Nuclear Science Addressing the Challenges of the Future Sal J. Golub, Office of Nuclear Energy, U.S. DOE: Harnessing Innovation to Expand the Benefits of Nuclear Power COFFEE BREAK 04 Kirsi Alm-Lytz, Director Nuclear Reactor Regulation, STUK, Finland: Progress and Experiences of the New NPP Projects in Finland 05 Nicholas Waeckel, EDF, France: New Challenges for Nuclear Fuel R&D 06 Geert-Jan de Haas, NRG, Petten, The Netherlands: Growing Pains: The Need for Restructuring the Cost Basis for Nuclear R&D

2 Lunch Session F1: LOCA I Session chair: C Struzik (CEA) / M Amaya (JAEA) Session secretary: J Takeuchi F1.1 HWR-1163 B. Baurens, Halden Project IFA LOCA test: In-pile Results F1.2 HWR-1164 P. Andersson, S. Holcombe and T. Tverberg, Halden Project Inspection of LOCA Test Rod IFA Using Gamma Emission Tomography F1.3 R. Szilard, C. L. Smith and R. C. Martineau, INL, USA A Demonstration of Advanced Safety Analysis Tools and Methods Applied to Large Break LOCA and Fuel Analysis for PWRs F1.4 L. E. Herranz and S. Bermejo, CIEMAT, Spain Assessment of FRAPTRAN-1.5 Capabilities for Clad-to-Coolant Heat Transfer Under Loss of Coolant Accidents Coffee break F1.5 A. Salatov et al, SC VNIINM, Russia Estimation of VVER Fuel Rods Failure Under LOCA Conditions F1.6 C. Struzik et al, CEA, France Main Improvements Done in ALCYONE Code in order to Describe LOCA Tests and Application to the IFA Calculation F1.7 I. Nagy et al, MTA, Hungary Integral Tests On the CODEX Facility to Simulate the Behaviour of VVER Fuel under Accident Conditions Demo and Display Session Display of instrumentation used in HBWR experiments MTO demos (see MTO programme for details) Tuesday May Session F2: Accident Tolerant Fuels and Advanced Reactor Technologies Session chair: H Teshima (MNF) / K Terrani (ORNL) Session secretary: R Szőke F2.1 J. Carmack and S. Bragg-Sitton, INL, USA Update on the U.S. DOE Accident Tolerant Fuel Development Program F2.2 H. Chichester et al, INL, USA Irradiation Testing Strategy for U.S. Accident Tolerant Fuels F2.3 H-G. Kim et al, KAERI, Korea Development Status of Surface Modified-Zr Cladding Concept for Accident Tolerant Fuels F2.4 HWR-1157 V. Andersson PIE on the Coated Fuel Rods from IFA-774

3 Coffee break F2.5 M. Kinoshita et al, Thorium Tech Opening World of Liquid Nuclear Fuel at Halden HBWR Solution, Japan F2.6 A. Kohyama, H. Kishimoto and J. S. Park, Muroran Institute of In-situ Neutron Irradiation Effects in SiC/SiC Fuel Pin Segments under Dynamic LWR Water Environment Technology, Japan F2.7 J. Daw et al, INL, USA Instrumentation for Accident Tolerant Fuel Loop Testing at ATR F2.8 K. Barrett et al, INL, USA Sensor Qualification Tests in Preparation for Accident Tolerant Fuels Water Loop Irradiation Testing in the Advanced Test Reactor at the INL F2.9 J. Hales and K. A. Gamble, INL, USA Modelling Accident Tolerant Fuel Concepts Lunch Session F3: Fuel and Cladding Performance Session chair: A Garde (Westinghouse) / V Tulkki (VTT) Session secretary: T Ikonen F3.1 HWR-1148 R. Szőke, Halden Project Summary of HRP/CEA Thermal-Hydraulic Analyses on the PWR Cladding Corrosion Tests IFA-708 and IFA F3.2 HWR-1098 H. K. Jenssen, Halden Project Post Irradiation Examination of IFA-708 Fuel Rods F3.3 R. Szőke, Halden Project Update on PWR Corrosion Test IFA F3.4 I. Arimescu, AREVA, USA Phenomenological Considerations regarding RX Zry-4 Free-stress Irradiation Growth to Assist Interpretation of the Halden IFA-653 test F3.5 J. Takeuchi, Halden Project Update on PWR Cladding Creep Test IFA F3.6 HWR-1189 V. Tulkki, VTT, Finland Analysis and Modelling of Halden Cladding Creep Experiments F3.7 HWR-1156 H. K. Jenssen, Halden Project PIE on the fuel Rods from the In-core Zircaloy Corrosion Test IFA Demo and Display Session Display of instrumentation used in HBWR experiments MTO demos (see MTO programme for details)

4 Wednesday May Session F4: Fuel Behaviour Testing and Modelling I Session chair: J Wright (Westinghouse) / J Klouzal (UJV Rez) Session secretary: S Holcombe F4.1 HWR-1159 T. Tverberg, Halden Project In-pile Results from the FGR Tests on MOX Fuel Disks in IFAs and F4.2 HWR-1152 H. K. Jenssen, Halden Project PIE of the High Burnup MOX Fuel Disk Rod from IFA F4.3 B. Boer et al, SCK-CEN, Belgium Irradiation of (Th,Pu)O2 Fuel under PWR Conditions in the BR-2 Reactor F4.4 A. Schubert et al, ITU, Germany Extension of the TRANSURANUS Burnup Model for (Th,Pu)O2 Type Fuel in Light Water Reactors Coffee break F4.5 HWR-1161 B. Baurens, Halden Project Update on the In-pile Results from the Fission Gas Release Mechanisms Study in IFA-716 after Final Unloading F4.6 HWR-1155 H. K. Jenssen, Halden Project PIE on the Six Test Rods from the FGR Test IFA F4.7 HWR-1141 T. Ikonen, Halden Project Monte Carlo Uncertainty and Sensitivity Analysis of the Power Determination in a Halden Test Rig Containing Multiple Rods F4.8 A. Casagranda et al, INL, USA Determination of Experimental Fuel Rod Parameters using 3D Modelling of PCMI with MPS Defect F4.9 S. Drera and Ø. Asphjell, Thor Accident Tolerant, Non-oxidizable MOX Fuel Energy AS, Norway TABLED F4.10 HWR-1088 H. K. Jenssen, Halden Project PIE of the High Burnup UO 2 Fuel Disk Rods from IFA and IFA Lunch Session F5: Plant Lifetime Extension Session chair: M Hiser (USNRC) Session secretary: K Hata F5.1 HWR-1150 K. Hata, Halden Project Final Report on the PWR Crack Growth Rate Investigation IFA F5.2 M. Ivanchenko, W. Karlsen and T. M. Karlsen, VTT, Finland Microstructural TEM Examination of 2 dpa Irradiated 304L Stainless Steel Extracted from a Tensile Creep Specimen from IFA F5.3 L. Zeng, NTÅF, Sweden More on Mixed Mode Cracking and Fracture Assessment of Mechanical Components in Nuclear Power Facilities

5 F5.4 M. Březina, J Petzová and L Kupča VUJE, Slovak Republic Samples Preparing and Determination of RPV Steel Properties before Irradiation in the Halden Reactor F5.5 T. M. Karlsen, Halden Project Update on the Materials Tests IFAs 733, 791 and F5.6 T. M. Karlsen, Halden Project In-pile Creep of ODS Steels Thursday May Session F6: LOCA II Session chair: M Bales (USNRC) Session secretary: J H Hansen F6.1 J. Zhang, A Dethioux and L. Oury, Tractabel, Belgium FRAPTRAN 1.5 Modelling of the Halden IFA650.9 and 10 LOCA Tests: Scoping Parametric Studies and Perspectives F6.2 L-O. Jernkvist and A. R. Massih, Quanmtum Technologies, Sweden Computational Assessment of Axial Fuel Relocation in Halden IFA-650 LOCA Tests F6.3 G. Pastore et al, INL, USA Modelling of LOCA Tests with the BISON Fuel Performance Code TABLED F6.4 HWR-931 B. C. Oberländer, Halden Project PIE Results from a High Burn-up (90 MWd/kgU) PWR Rod Subjected to a High Temperature Transient in the LOCA-Test IFA TABLED F6.5 HWR-1019 B. C. Oberländer, Halden Project PIE on the LOCA Test of High Burn-up PWR fuel (61 MWd/kgU) in IFA TABLED F6.6 HWR-1020 B. C. Oberländer, Halden Project PIE on the LOCA Test of VVER Fuel (56MWd/kgU) in IFA TABLED F6.7 HWR-1044 B. C. Oberländer, Halden Project PIE on the Non-burst LOCA Test of BWR Fuel (56MWd/kgU) in IFA Coffee break Session F7: Fuel Behaviour Testing and Modelling II Session chair: M Petit (IRSN) / A Lavoil (EDF) Session secretary: B Baurens F7.1 B. Volkov, Halden Project Gadolinium Doped VVER Fuel Irradiation in IFA F7.2 HWR-1091 H. K. Jenssen, Halden Project PIE of Four UO 2 VVER-1000 Fuel Rods for IFA F7.3 G. Pastore et al, INL, USA Modelling of the Gadolinium Fuel Test IFA-681 using the BISON Code F7.4 HWR-1094 H. K. Jenssen, Halden Project PIE of 6 UO 2 Fuel Rods for IFA Lunch Session F7 (cont): Fuel Behaviour Testing and Modelling II F7.5 HWR-1158 J. Takeuchi, Halden Project Overpressure Testing of an M-MDA-SR PWR Fuel Rod in IFA

6 F7.6 G. Khvostov and W. Wiesenack, Analysis of Halden Overpressure Tests Using the FALCON Code PSI, Switzerland F7.7 HWR-1153 H. K. Jenssen, Halden Project PIE of the VVER Fuel Segment from the FGR Test in IFA F7.8 HWR-1154 H. K. Jenssen, Halden Project PIE on the gadolinia fuel segments from the FGR test in IFA Coffee break F7.9 K. Terrani et al, ORNL, USA Advanced Electron Microscopy Characterization of High Burnup Structure F7.10 HWR-1162 W. Wiesenack, Halden Project Analysis of the In-pile Fuel Thermal Conductivity Degradation test IFA F7.11 HWR-1160 J. Takeuchi, Halden Project Uncertainty Analyses on the Fuel Creep Test IFA F7.12 D. Magnusson Actinide Recovery for Advanced Nuclear Fuel Cycles F7.13 HWR-1165 S. Holcombe et al, Halden Project Non-destructive Determination of the Rod-wise Fission Gas Release Fraction Using Gamma Emission Tomography on Complete Fuel Assemblies