High Temperature corrosion and material testing in hot helium

Transcription

1 Centrum výzkumu Řež, s.r.o High Temperature corrosion and material testing in hot helium J. Kalivodová, J. Berka 9th International school on nuclear power; WORKSHOP V VINCO TECHNICAL MEETING, November 17th, 2017, Warsaw, Poland

2 High Temperature Corrosion or dry corrosion or scaling = a chemical attack from gases, solid or molten salts, or molten metals, typically at temperatures above (400 C) Environment Understanding of behaviour of materials in aggressive environments: High Temperature HT oxidation HT carburization HT nitridation HT graphitization Liquid metal corrosion and embrittlement Hydrogen attack Molten salt corrosion HT Creep Thermal Fatigue Erosion SCC Common material related issues for nuclear and no-nuclear energy sector: Understanding of material degradation in aggressive environments HT material development: advanced steels, alloys, coatings and ceramic materials New manufacturing processes of advanced materials Standard material characterisation, testing and evaluation Combination of advanced experimental characterization of materials with multiscale modelling

3 High Temperature Corrosion - oxidation Oxidation - by far the most common form of high-temperature corrosion - almost all alloys and materials oxidize and corrode above a certain T Scaling - Nature of the corrosion products Loss of material - Rate of corrosion Changes in physical properties - Mechanism (Kofstad, 1988). Oxidation of SiCf/SiC: SiC with O2 and moisture at elevated temperatures: Passive layer protecting SiC+O2=>SiO2+C. Active oxidation SiC+O=>SiO+CO 1300 C Bubble formation, grow, rupture = loss of mass

4 Motivation: High-temperature helium reactor technologies research and development Main areas of He tech. research at CVR: Extending the existing knowledge of material properties and behavior under high temperature He environments, including also irradiation Purification/chemical composition/recycling of He gaseous coolant Studying thermodynamic and thermalhydraulic properties of He GFR vs V/HTR In common : Technology of He circuits & components High temperature materials Possibility of nuclear cogeneration He C; 7MPa HTHL-2 Our facilities supporting R&D for HTR/GFR reactor systems S-Allegro loop High Temperature Helium Loops (HTHL-1 and 3) - out of pile High Temperature Helium Loop (HTHL-2) in pile High Temperature Furnaces (HTF) HTF

5 Tested materials in HT helium so far F/M steel: P91 AS: 316L Alloy 800H, Welded Alloy 800H Selected GFR&V/HTR concept materials GFR V/HTR Component Material T ( C) Material T ( C) Reactor vessel 9-12Cr F/M 400/ Cr F/M 450/1000 AISI 316LN IHX/SG IHX Alloy Alloy IN 617 IN 617 Haynes230 SiC Secondary pipe work Alloy 800, ODS, IN Alloy 800, ODS, IN Core support structure 15Cr-15Ni Ti SiCf/SiC SiC Coating UCO or Fuel cladding 15Cr-15Ni Ti UO2 kernel (TRISO) SiCf/SiC Mo alloy *Courtesy of GIF VHTR PMB IN 713, 738, 617 Fe-Cr-Al WM HAZ SiCf/SiC Corund based ceramics- Lunit 73 (C610), Luxal 203 (C799), AG 202 (C795)

6 High Temperature Helium Furnace & microstructural evaluation Horizontal furnace Atmospheric pressure up to approx. 5 bar Flow rate: 0,1 l/min Temperature: up to 900 C Inlet: premixed gas mixture Gas analysis: GC HID, online H2O, O2 Columnwithmoledcular sieve(gasdryer) V-8 Gasmixture P-20 Moisturecontroler (BARTEC) Flowcontroler F P-14 Specimens Test furnace V-9 Samples: - Corrosion coupons - Tubular FIB SEM/EDX Sample evaluation after exposure: gravimetry, metallography, hardness, nanoindentation, microstructural characterization FIB- SEM/EDX, WDS, EBSD; TEM, SIMS

7 High Temperature Helium Loops (HTHL-1 and HTHL- 2*) Loop components and systems: Active test channel material testing under HT helium and irradiation; heat exchanger zone, heater and space for samples Purification system: Mechanical filter transient and solid particles removal CuO oxidizer further oxidation of gas impurities Molecular sieve beds Double parallel adsorbers with on line regeneration- transient removal Impurity dosing system is used for He, CO, CO2, CH4, H2, O2 dosing HTHL-2 in pile He purity control system HTHL-1 Active chanel - HTHL-1 Experimental conditions: Temperature: 900C Pressure up to 7MPa Gas velocity: 20m/s HTHL-2: neutron irradiation Coolant monitoring system: temperature, pressure, flow rate, on-line: moisture content, oxygen content and FTIR analyser; off-line: MS-GC gas analysis HTHL-2 in pile

8 HTHL3 simulating GFR fuel cladding conditions Experimental conditions: Temperature: 900C Pressure up to 7MPa Gas velocity: 90m/s Samples: tubular samples HTHL3: test section HTHL3: sample holder with SiCf/SiC samples HTHL 3 Page 8

9 Experimental helium loop S-Allegro Purpose: Verify the basic safety features and system behavior of the GFR concept, the demonstrator reactor ALLEGRO The main function is to verify the decay heat removal system using dedicated DHR loop Parameters: 1 primary loop, 1 DHR loop, medium: He Pressure: 7 MPa Power: 1 MW (electric power), T in (model core): 400 C T out (model core): 850 C Flow rate (I. loop): 0,5 kg/s 1 MW coiled tube heat exchanger (He/He) (T (I.): C; T (II.): C) Heat exchanger He circulator Coaxial valve DHR loop Page 9

10 Projects International and national collaboration International projects (Euratom): FP7 ARCHER ( ): extended the state-of-the-art European (V)HTR technology basis with generic technical effort in support of nuclear cogeneration demonstration FP7 MATISSE ( ): Support to the development of joint research actions between national programs on advanced nuclear materials VINCO (H2020) ( ): Visegrad Initiative for Nuclear Cooperation to strengthen public awareness about advanced nuclear reactors, mainly gas cooled systems (GFR, HTR) GEMMA (H2020) ( ): to qualify and codify the selected structural materials for the construction of Generation IV reactors GEMINI+ (H2020) ( ): together with the NGNP Industry Alliance in the GEMINI Initiative to support a development of the demonstrator (HTGR modular system) to be used for high temperature nuclear cogeneration National projects (Czech Republic): ČiPErA - TA ( ): Technologies for gas purification and sealing for advanced applications in nuclear and non-nuclear energetic applications TEQUILA - TA ( ) : Development of equipment for separation of noble gases from helium ARMAT - TA ( ) : Materials for advanced nuclear reactors and other energy applications MPO TRIO Heat exchanger for HT& HP applications- FV10472 ( ) INOVMAT - TH ( ): Development of High Temperature Heat Exchangers Using, Advanced Manufacturing Technologies, Mechanical Design and Materials REGNET - TH ( ): Joint leakage optimization and determination and helium recovery from coolant leakage in generation four helium cooled reactors

11 Other Participation in international platforms/organizations: Participation in Joint Program Nuclear Materials at European Energy Research alliance (EERA) EU representative PMB VHTR MAT of GIF Member of Task Force Nuclear Cogeneration Industrial Initiative (NC2I) and GEMINI Initiative Selected literature: J. Berka, M. Vilémová, P. Sajdl: Testing of degradation of alloy 800 H in impure helium at 760 C, Journal of Nuclear Materials 464 (2015) J. Berka, J. Kalivodová: Testing of high temperature materials within HTR program in Czech Republic, EPJ Nuclear Sci. Technol. 2, 24 (2016) K. Kunzová, J. Berka, J. Siegl, P. Haušild: Effect of thermal exposure in helium on mechanical properties and microstructure of 316L and P91, Journal of Nuclear Materials 472 (2016) D. Marušáková, P. Bublíková, J. Berka, Z. Vávrovcová, J. Burda: Microstructural analysis of 800H steel exposed at test operation in HTHL by using FIB-SEM and HRTEM techniques, Applied Surface Science 416 (2017)

12 Thank you for your attention! Centrum výzkumu Řež Hlavní Husinec-Řež Czech Republic EVROPSKÁ UNIE EVROPSKÝ FOND PRO REGIONÁLNÍ ROZVOJ INVESTICE DO VAŠÍ BUDOUCNOSTI