| 01-JUN-23 | CSNI2045 | THAI-3, Thermal-hydraulics, Hydrogen, Aerosols, Iodine (ThAI) Project, Third phase (2016-2019) (Arrived) |
| 01-FEB-23 | CSNI2044 | ATLAS-2 PROJECT, 2nd Phase of The Advanced Thermal-hydraulic Test Loop for Accident Simulation Project (Arrived) |
| 24-JAN-23 | NEA-1664 | IFPE DATABASE, International Fuel Performance Experiments Database (Arrived) |
| 16-JAN-23 | NEA-1615 | IFPE/CEA-DEFECT FUEL, Experiments Irradiated at CEA Grenoble (Arrived) |
| 16-JAN-23 | NEA-1773 | IFPE/IFA-591, JAEA Power Ramp Tests of MOX Fuel Rods IFA-591 (Arrived) |
| 16-JAN-23 | NEA-1722 | IFPE/ROPE-1, BWR, 4 rods, Ringhals, investigates clad creep-out from Studsvik (1986-1993) (Arrived) |
| 16-JAN-23 | NEA-1778 | IFPE/IFA-514/565, LWR MOX Fuel Irradiation Tests - HBWR Irradiation with the Instrument Rig, (JAEA) 6 rods (Arrived) |
| 16-JAN-23 | NEA-1594 | IFPE/AEAT-IMC, Onset Gas Release and Grain Face Venting Rates in Fuels (Arrived) |
| 16-JAN-23 | NEA-1599 | IFPE/FUMEX-1, Data from OECD Halden Reactor Project for FUMEX-1 (Fuel Modelling at Extended Burnup) (Arrived) |
| 16-JAN-23 | NEA-1596 | IFPE/AECL-BUNDLE, Fission Gas Release and Burnup Analysis, PHWR Fuel (Arrived) |
| 16-JAN-23 | NEA-1645 | IFPE/EFE-RO, Experimental Fuel Elements RO89 and RO51 in TRIGA 14 MW Reactor (INR-Pitesti) (Arrived) |
| 16-JAN-23 | NEA-1777 | IFPE/CANDU-IRDMR, In-Reactor Diameter Measuring RIG EXP-FIO-118 and EXP-FIO-119 Fuel Behaviour under LOCA Conditions (Arrived) |
| 16-JAN-23 | NEA-1783 | IFPE/CANDU-FIO-131, CANDU experiment FIO-131 Fuel Behaviour under LOCA Conditions (Arrived) |
| 16-JAN-23 | NEA-1841 | IFPE/EXP-BDL-406, performance of natural UO2 fuel irradiated at low linear powers in NRU (Arrived) |
| 16-JAN-23 | NEA-1858 | IFPE/CANDU-FIO-130, CANDU experiment FIO-130 Fuel Behaviour under LOCA Conditions (Arrived) |
| 16-JAN-23 | NEA-1548 | IFPE/IFA-535.5&6, Fission Gas Release, Power Ramps, High Burnup Fuel (Arrived) |
| 16-JAN-23 | NEA-1625 | IFPE/GAIN, Gadolinia Doped UO2 Fuel Behaviour Experiment (Arrived) |
| 16-JAN-23 | NEA-1560 | IFPE/BR3-HBFRHCP, BR-3 High Burnup Fuel Rod Hot Cell Program (Arrived) |
| 16-JAN-23 | NEA-1557 | IFPE/SUPER-RAMP, PCI Failure Threshold for PWR and BWR Fuels (Arrived) |
| 16-JAN-23 | NEA-1310 | IFPE/SOFIT, WWER-440 Fuel Thermal Performance and Fission Gas Release (Arrived) |
| 16-JAN-23 | NEA-1677 | IFPE/ZAPOROSHYE-V1K, Zaporoshye VVER1000 fuel behaviour data (4-8 cycles, Burnup about 50 MWd/kgUO2) (Arrived) |
| 16-JAN-23 | NEA-1741 | IFPE/NOVOVORONEZH, operation factor data of the Novovoronezh VVER-1000 fuel assembly 4108 rods (Arrived) |
| 16-JAN-23 | NEA-1799 | IFPE/AEKI-EDB-E110, Experimental Database of E110 Claddings under Accident Conditions (Arrived) |
| 16-JAN-23 | NEA-1861 | IFPE/IFA-629.1, The Re-irradiation of MIMAS-MOX Fuel in IFA-629.1 (Arrived) |
| 16-JAN-23 | NEA-1510 | IFPE/HBEP, Battelle's High Burn-Up Effects Programme for Fuel Performance (Arrived) |
| 10-NOV-22 | NEA-1486 | ICSBEP2021-HANDBOOK, International Criticality Safety Benchmark Experiment Handbook (Arrived) |
| 09-NOV-22 | NEA-1765 | IRPHE2021-HANDBOOK, International Handbook of Evaluated Reactor Physics Benchmark Experiments (Arrived) |
| 21-JUL-22 | NEA-1849 | ZZ PSBT, NUPEC PWR Sub-channel Bundle Tests Benchmark (Arrived) |
| 16-JUN-22 | NEA-1926 | N-THERMALISATION, Notes on the scattering of thermal neutrons (Arrived) |
| 15-JUN-22 | NEA-1925 | TCOFF, Thermodynamic Char. of Fuel Debris and Fission Products based on Scenario Analysis of Severe Accident Progression (Arrived) |
