Material characterization Capabilities at IFE Kjeller (NMAT)

Transcription

1 Material characterization Capabilities at IFE Kjeller (NMAT) NOMAGE4, Halden 31.10& Institute for Energy Technology Sector: Nuclear Safety & Reliability NUSP, Head: Dr. M.McGrath Department: Nuclear Materials Technology NMAT Head: Dr. B.C.Oberländer P.O.Box 40, N-2027 Kjeller, Norway

2 Institutt for energiteknikk Since 1951 Norway has Heavy Water research Reactors operated by the Institutt for energiteknikk (IFE), JEEP II, max. effect of 2 MW, is located at Kjeller near Oslo, Halden Reactor, max effect 25 MW, is located at Halden, 140 km south of Kjeller. X Kjeller X Halden NMAT, Kjeller, supports both reactors with fuel and hot cell services.

3 NMAT capabilities NMAT (12 employees) Post irradiation examination of nuclear fuel (PIE) Fabrication of fresh standard & experimental nuclear fuel (up to 20 % enrichment) Refabrication and instrumentation of pre-irradiated nuclear fuel Service and Maintenance Nuclear waste handling Intermediate storage of fresh and spent fuel Safety and Saveguarding

4 Fuel cycle and PIE facilities Fuel cycle facilities Hot Cell Labs Pilot production plant for UO2-fuel Alpha lab with glove boxes equipped for MOX fuel rod production Concrete shielded cells 4 PBq = 4x10eks15 Bq Intermediate storage pits for spent fuel Lead shielded cells

5 Fuel Production Laboratory The laboratory has a complete line for UO 2 - pellet production (milling, sifting, mixing, pressing (various enrichments & dimensions), sintering, grinding, drilling, cutting, quality control, etc). The laboratory produces ca. 200 kg fuel pellets p.a for HBWR and JEEPII. Fuel pellets (e.g. PWR, BWR, Booster, 5th Charge, JEEP2) for standard and experimental fuel rods. The alpha/mox laboratory is equipped for fabrication and instrumentation of MOX-containing fuel rods. The laboratory is not equipped for production of MOX pellets from powder. Various quality control tests can be performed/ MOX

6 Post-irradiation examination (PIE) capabilities at Kjeller (1 of 3) PIE, non-destructive test methods Visual inspection Profilometry & dimensional measurements Eddy current testing Neutronradiography -scanning of fuel -scanning of plenum / Kr-85 method for non-destruction determination of released fission gas

7 Facility: Jeep II reactor with its experimental beam channels is used in Neutronradiography

8 Neutron radiography Fuel rod features (fuel rod integrity, relocation of pellets, fuel cracking, PCMI) Instrumentation Hydrogen in cladding / moisture in fuel rod Resolution: 50 m Stitching and ing of digital images

9 PIE capabilities at Kjeller (2 of 3) Destructive structural PIE & chemical analysis of nuclear fuel Puncturing & fission gas analysis Chemical dissolution of fuel / Sampling for burn-up & analysis / retained fission gas analysis Hydrogen in clad - melt extraction analysis Metallography / Ceramography Optical microscopy, SEM, Analytical SEM (EDS) of oxides and metals Quantitative image analysis (grains, pores, MFP, oxide layer etc) Micro -scanning and autoradiography Fuel density O/U ratio (oxidation of fuel) Raman spectroscopy oxide characterisation Cutting for TEM foil preparation

10 Remote handled anaytical SEM Study of irradiated steels, Zry & fuel (replicas or miniature specimens) Hot-cell modified, partial shielding SEM: Jeol 6100 (1995) 10x - about x up to 30 kv SEI, BEI detectors EDX-Detector/Analysing System (2011) SemAfore digital image recording

11 SEM fracture surface morphology and microstructure details (replica technique)

12 PIE capabilities at Kjeller (3 of 3) Destructive mechanical PIE Tensile testing Hardness testing Burst testing Stress-corrosion cracking PIE of steels Characterisation of fracture surfaces (SEM) Microstructure metallography Mechanical properties Electronic data aquisition & treatment

13 Visual inspection, metallography ceramography, hydrogen analysis, tensile testing

14 Refabrication & Instrumentation of Irradiated Fuel Rods Refabrication of irradiated experimental fuel rods (UO 2, MOX) Encapsulation (AGR rods) Preparation of irradiated fuel segments & attachment of instrumented endplugs to the segments Endplug instumentation TF:Temperature Fuel PF: Pressure Fuel EC: Elongation Clad TC: Temperature Clad Available remote handled in-cell machines Cutting & Grinding Unit (Lathe) Drilling & Freezing Unit (Lathe) Welding&Pressurisation Unit Milling machine

15 Re-fabrication & instrumentation of irradiated fuel rod segments Remote handled in-cell machines are in operation since 1991 BU of re-fabricated & instrumented rods was up to 100 MWd/kg U >130 fuel UO2 / MOX rods were re-fabricated and/or instrumented > 40 rods were equipped with a thermocouple

16 Remote handled milling machine in hot cell For fabrication of test samples from irradiated material, i.e. CTs, tensile specimens Modified, remote handled milling machine installed in concrete cell. The milling machine is operated with MS manipulators. Electric control unit and steering box separate from the machine. Special specimen jig and tool change fittings. The milling machine is installed in a containment box (milling particles) A central vacuum cleaner removes particles from milling

17 Machining of Test Samples from Irradiated Materials Specimen preparation from irradiated steel and Zircaloy for corrosion and mechanical testing (CT Specimens, etc.) Operations: Cutting, Milling, Welding

18 Facility: Dry storage pits for spent fuel & semi annual IAEA Inspection