LNM: Labor für Nukleare Materialien
26
0
0
Volltext
(2) Table of Contents o Introduction • LNM Mission • Background / Aspects of Nuclear Materials • Research Programs in LNM o Examples from Research Programs • Pressure Boundary Components / RPV Internals (INTEGER) − SCC in Ni-Alloys and Weldments in LWRs − … effect of hydrogen on SCC initiation in Alloy 182 − … SCC resistance and fracture toughness on mock-up weld on Alloy 52M • Cladding & Fuel (Nuclear Fuels) − Hydride (Re-)Orientation − … under fatigue − … investigation using neutrons − … liner cladding and H distribution • Advanced Systems (Advanced Nuclear Materials) − Spallation material investigations (from STIP) − … material flow using new sample preparation box and FIB − … example using atom probe tomography. M.A. Pouchon, NES Information Event, 24.10.2017, Page 2 / 26.
(3) Table of Contents o Introduction • LNM Mission • Background / Aspects of Nuclear Materials • Research Programs in LNM o Examples from Research Programs • Pressure Boundary Components / RPV Internals (INTEGER) − SCC in Ni-Alloys and Weldments in LWRs − … effect of hydrogen on SCC initiation in Alloy 182 − … SCC resistance and fracture toughness on mock-up weld on Alloy 52M • Cladding & Fuel (Nuclear Fuels) − Hydride (Re-)Orientation − … under fatigue − … investigation using neutrons − … liner cladding and H distribution • Advanced Systems (Advanced Nuclear Materials) − Spallation material investigations (from STIP) − … material flow using new sample preparation box and FIB − … example using atom probe tomography. M.A. Pouchon, NES Information Event, 24.10.2017, Page 3 / 26.
(4) Mission of LNM •. CENTRE OF EXCELLENCE: The LNM is national centre of excellence in Switzerland in the domains of (irradiated) materials behaviour and ageing in nuclear installations.. •. ACADEMIC R&D & SCIENTIFIC SERVICE Sustainability of current and future nuclear installations for electricity & heat generation as well as to the performance of nuclear facilities. A special emphasis is placed to the safety & safe long-term operation of the CH NPPs. • Material ageing in the primary circuit and its impact on integrity, safety & lifetime • Performance and safety of LWR core materials in service and storage • Radiation damage in structural and core/target materials of advanced nuclear and accelerator systems. • Material irradiation program at SINQ in co-operation with the Spallation Neutron Source Division. • Post-irradiation examinations and failure analysis in close cooperation with the Hotlab Division AHL.. M.A. Pouchon, NES Information Event, 24.10.2017, Page 4 / 26.
(5) Mission of LNM •. KNOWLEDGE MANAGEMENT: Academic teaching and education as well as in knowledge transfer contributing to the education of the future nuclear specialists and preservation of expertise & excellence. •. INDEPENDENT EXPERTISE: Independent expertise and excellence for Swiss safety authority, e.g. for expertise’s and consulting (TSO) industry, e.g., for material examinations and failure analysis.. •. STATE OF THE ART INFRASTRUCTURE: State-of-the-art lab & computing infrastructure and modelling tools for: characterization of (radioactive) materials analysis & prediction of the material behavior, integrity, safety & lifetime (strongly benefiting from PSI’s unique large scale facilities: hotlab, SLS, SINQ, SwissFEL). M.A. Pouchon, NES Information Event, 24.10.2017, Page 5 / 26.
(6) Background - Programs Today in CH. LWRs. High T Fast n. ADS Spallation. Nuclear Fuels. Component Structural Integrity. Advanced Nuclear Materials. M.A. Pouchon, NES Information Event, 24.10.2017, Page 6 / 26.
(7) Projects overview ANM: • MeAWaT - ETH competence center CCEM • 3D Printing - ETH scientific focus area – additive manufacturing • MatISSE, SOTERIA, INSPYRE, M4F - European projects • STIP irradiation program / PIE - CAS, JAEA, USTB, Beijing University, HFUT NF: • Cladding Mechanical Behavior and Influence of Hydrogen (dry storage, …) - swissnuclear, ESB • Hydrogen uptake - swissnuclear, MUZIC • ATF - CARAT, swissnuclear, KKG • Fuels - swissnuclear, Areva, Westinghouse, NFIR • FIB – R’Equip. INTEGER: • PISA-II & -ext, PARENT, NORA-II, SAFE-II LEAD, PROBAB, NORA-III - ENSI • PLiM-VI - swissnuclear • Helium FM - fusion/STIP-V • SOTERIA, INCEFA+, NOMAD, MEACTOS, M4F - European projects • YUMOD (KKL), SCC Alloy 52 (KKL), BWRVIP-233(EPRI), EAF LAS (EPRI) M.A. Pouchon, NES Information Event, 24.10.2017, Page 7 / 26.
(8) Table of Contents o Introduction • LNM Mission • Background / Aspects of Nuclear Materials • Research Programs in LNM o Examples from Research Programs • Pressure Boundary Components / RPV Internals (INTEGER) − SCC in Ni-Alloys and Weldments in LWRs − … effect of hydrogen on SCC initiation in Alloy 182 − … SCC resistance and fracture toughness on mock-up weld on Alloy 52M • Cladding & Fuel (Nuclear Fuels) − Hydride (Re-)Orientation − … under fatigue − … investigation using neutrons − … liner cladding and H distribution • Advanced Systems (Advanced Nuclear Materials) − Spallation material investigations (from STIP) − … material flow using new sample preparation box and FIB − … example using atom probe tomography. M.A. Pouchon, NES Information Event, 24.10.2017, Page 8 / 26.
(9) SCC in Ni-Alloys and Weldments in LWRs Current activities: •. SAFE-II (ENSI): Subproject-I: PhD thesis of J. Bai on the Effect of hydrogen on SCC initiation in Alloy 182 under BWR/HWC conditions @ 274 °C. •. MICRIN+ (EU-7 /NUGENIA+): Accelerated screening test method for SCC initiation studies. •. ICG-EAC Round Robin (in-kind): SCC initiation study in Ni-alloys under constant load. •. MEACTOS (H2020 EURATOM): Mitigating environmentally-assisted cracking through optimisation of surface condition. •. ECG-COMON Round Robin (in-kind): Effect of hydrogen on the corrosion behaviour and oxide films in Ni, Alloy 600 and Alloy 182. •. Overlay repair weld with Alloy 52M (KKL, service project): Characterization of SCC resistance and fracture toughness on mock-up weld. M.A. Pouchon, NES Information Event, 24.10.2017, Page 9 / 26.
(10) SAFE-II SP-I: SCC Initiation in Alloy 182 Dissimilar Metal Welds. PhD project of J. Bai: • Background: SCC incidents in Alloy 182 DMWs in BWRs • Effect of H2 on SCC initiation & short crack growth in Alloy 182 under BWR/HWC conditions @ 274°C • Identification of optimal mitigation conditions • Tentative mechanistic interpretation on mechanism. Maximum in SCC initiation susceptibility & SCC crack growth rate at Ni/NiO phase boundary! M.A. Pouchon, NES Information Event, 24.10.2017, Page 10 / 26.
(11) EBSD Analysis of IGSCC Initiation & Propagation. All grain boundaries in original material. • •. All cracked grain boundaries. Low angle grain boundaries seem to be resistant to SCC. Random high-energy, high-angle grain boundaries (HABs) with higher number of Schmid factor mismatch between the adjacent grains are prone to SCC → strain/deformation incompatibility plays a key role in crack initiation & propagation M.A. Pouchon, NES Information Event, 24.10.2017, Page 11 / 26.
(12) Material Characterization on Alloy 52 for KKL Axial SCC crack in N5 RPV FW nozzle ~ 93 % of wall thickness. Full structural overlay repair weld with Alloy 52M. • Request of ENSI for additional material tests with Alloy 52M to confirm the assumptions of the performed integrity assessment • Tensile and EPFM tests in air, SCC test in high-temperature water • Very high SCC resistance & high toughness confirmed • KKL & ENSI were highly satisfied by professional PSI work. M.A. Pouchon, NES Information Event, 24.10.2017, Page 12 / 26.
(13) Table of Contents o Introduction • LNM Mission • Background / Aspects of Nuclear Materials • Research Programs in LNM o Examples from Research Programs • Pressure Boundary Components / RPV Internals (INTEGER) − SCC in Ni-Alloys and Weldments in LWRs − … effect of hydrogen on SCC initiation in Alloy 182 − … SCC resistance and fracture toughness on mock-up weld on Alloy 52M • Cladding & Fuel (Nuclear Fuels) − Hydride (Re-)Orientation − … under fatigue − … investigation using neutrons − … liner cladding and H distribution • Advanced Systems (Advanced Nuclear Materials) − Spallation material investigations (from STIP) − … material flow using new sample preparation box and FIB − … example using atom probe tomography. M.A. Pouchon, NES Information Event, 24.10.2017, Page 13 / 26.
(14) Transportation of spent fuels, dry storage Cladding fatigue risk. Credit: Zwilag. Credit: NAGRA. M.A. Pouchon, NES Information Event, 24.10.2017, Page 14 / 26.
(15) Hydride (Re-)Orientation – Impact on Fatigue H-free, as-received. ‘Normal’ appearance. F In-plane hydrides. F. Deep splits No lifetime reduction detected. Reoriented hydrides. W. Gong, A. Brenin, R. Zubler, J. Bertsch, Hydrides Impact on Zircaloy Fatigue Properties, , WRFPM, Sep. 10-14, 2017, Jeju, Korea. Facetted due to hydrides Lifetime reduction unclear Further tests needed. M.A. Pouchon, NES Information Event, 24.10.2017, Page 15 / 26.
(16) Neutron Radiography at PSI SINQ Spatial resolution. neutrons. Neutron microscope neutrons. SINQ spallation neutron source M.A. Pouchon, NES Information Event, 24.10.2017, Page 16 / 26.
(17) Ex-situ Measurements – H & Stress pre-test. post-test (350°C, 120 MPa nom., 10 h, 240 wppm H). Hydrides metallography. H concentration Calibration. 0.016 transmission increase. ~160wppm H elevated by stress. M.A. Pouchon, NES Information Event, 24.10.2017, Page 17 / 26.
(18) Liner Cladding – Quantification H content DX-D4 outer liner cladding, ~200 wppm H 4.5 mm segment // neutron beam POLDI thermal neutron beamline, exposure 3 min x 100. Further tests with different cooling rates already performed. hydrides free. hydrides present. Neutron image M.A. Pouchon, NES Information Event, 24.10.2017, Page 18 / 26.
(19) Table of Contents o Introduction • LNM Mission • Background / Aspects of Nuclear Materials • Research Programs in LNM o Examples from Research Programs • Pressure Boundary Components / RPV Internals (INTEGER) − SCC in Ni-Alloys and Weldments in LWRs − … effect of hydrogen on SCC initiation in Alloy 182 − … SCC resistance and fracture toughness on mock-up weld on Alloy 52M • Cladding & Fuel (Nuclear Fuels) − Hydride (Re-)Orientation − … under fatigue − … investigation using neutrons − … liner cladding and H distribution • Advanced Systems (Advanced Nuclear Materials) − Spallation material investigations (from STIP) − … material flow using new sample preparation box and FIB − … example using atom probe tomography. M.A. Pouchon, NES Information Event, 24.10.2017, Page 19 / 26.
(20) STIP program – Materials in Spallation Target. Embrittlement of FM Steels (high He production) M.A. Pouchon, NES Information Event, 24.10.2017, Page 20 / 26.
(21) Analysis Tools – Connection Through FIB Spallation Materials. NPPs. Hot Cells. Hotlab Preparation box. Hotlab-FIB. nm Mechanical Testing. Microscopy / APT. μm - mm Beam Line Techniques. M.A. Pouchon, NES Information Event, 24.10.2017, Page 21 / 26.
(22) APT – Sample prep. lift out. Activity for a TEM sample: · 106 Bq. Pt pre-welding. Pre-tip. Sample Pt Pre-tip Sharpening Pt pre-welding. Pt welding Activity for APT sample: 1.4·10-3 Bq M.A. Pouchon, NES Information Event, 24.10.2017, Page 22 / 26.
(23) APT - Background. E ≈ 10...30. mass to charge ratio of the ions allows to determine their chemical nature. V nm. m t = 2 ⋅ e(VO + VP ) ⋅ n L t1. t2. 50000. 2. Number of atoms. electric field is induced at the apex of a tip. 40000. 57Fe2+. 20000 53Cr2+ 50Cr2+. 58Fe2+. 0 24. 25. 26. 27. Mass spectrum of Fe-Cr alloy +. 56Fe2+. 30000. 10000 +. 54Cr2+ 54Fe2+. 52Cr2+. 28. 29. 30. 30×30×100nm3. V 0 + VP. V0. few Mega atoms M.A. Pouchon, NES Information Event, 24.10.2017, Page 23 / 26.
(24) proton irradiation. APT Results - Example. Material: Fe-8Cr-2W-0.1C-0.2V-0.04Ta martensitic steel F82H Japanese reduced activation steel, fusion structural material, also candidate for GenIV Exposure: Irradiation in SINQ target (STIP II), to 20 dpa at 350°C CV>1at% CW>4at%. С-enriched clusters:. CCr>15at% 15×33×37 nm3. CTi>5at% 15×33×37 nm3. F82H, 20 dpa, 350°C. CC>2at%. С-enriched clusters:. • on the loops or in its neighborhood • (Cr, W, V, Ti and Fe) to C ratio ≈ 17 to 1, M18C carbide Chi (χ) -phase? • But: no data about such phases in F82H radiation induced M.A. Pouchon, NES Information Event, 24.10.2017, Page 24 / 26.
(25) Wir schaffen Wissen – heute für morgen Nuclear Materials Research at PSI is active… … serving the authorities and industry with safety investigations. … helping the industry with performance optimizations. … contributing to education and training. … contributing to the next generation research..
(26) Wir schaffen Wissen – heute für morgen My thanks go to • All the members of LNM for their great efforts & performance • AHL / SU / NES / NUM • All external partners like ENSI, swissnuclear, CCEM, SNF, …. LNM & Friends.
(27)
ÄHNLICHE DOKUMENTE
33 DOE, Office of Health, Safety, and Security, Independent Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project (Washington,
Moreover, a GIS database was developed for the dams to assess the structural and non-structural damages, while creating access to a wide range of descriptive information,
In a long-term research strategy, the German higher federal authorities responsible for hu- man and environmental safety – the German Environment Agency (UBA), the Federal Insti-
The Federal Institute for Occupational Safety and Health (BAuA) conducts research and development in the field of safety and health at work, promotes the transfer of knowledge
Keywords: REACH; Occupational health and safety; Derived no-effect level; Chemical safety report; Exposure scenario; Safety data sheet; Worker legislation; Worker; Registration;
An analysis of the development shows that overall in the EU, in Germany, in France, in Austria and in Slovenia the number of employees in the FS industry has increased in
Abstract: The Swiss Feed Data Warehouse is a public service for companies, farmers and research institutions that provides detailed and up-to-date information about the con-
An introduction and historical background are provided on vaccines, vaccine development, national immunisation policy and programmes, vaccine safety and
