Plasma‐material Interactions Problems and Dust Creation and Re‐suspension in Case of Accidents in Nuclear Fusion Plants: A New Challenge for Reactors like ITER and DEMO
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Andrea Malizia | A. Murari | Michela Gelfusa | S. Talebzadeh | J. F. Ciparisse | L. A. Poggi | Pasqualino Gaudio | A. Murari | M. Gelfusa | A. Malizia | P. Gaudio | J. Ciparisse | S. Talebzadeh | L. Poggi
[1] Jon C. Helton,et al. Summary description of the methods used in the probabilistic risk assessments for NUREG-1150 , 1992 .
[2] Ch. Linsmeier,et al. Oxidation behaviour of silicon-free tungsten alloys for use as the first wall material , 2011 .
[3] V. Philipps,et al. Plasma Wall Interaction and Its Control by Wall Conditioning , 2004 .
[4] Huijun Li,et al. A brief summary of the progress on the EFDA tungsten materials program , 2013 .
[5] R. L. Klueh,et al. Ferritic/martensitic steels for advanced nuclear reactors , 2009 .
[6] Kazuyuki Takase,et al. Temperature distributions in a Tokamak vacuum vessel of fusion reactor after the loss-of-vacuum events occurred , 1998 .
[7] R. Doerner,et al. Particle-induced erosion of materials at elevated temperature , 2004 .
[8] H. Bolt,et al. Self passivating W-based alloys as plasma-facing material , 2009 .
[9] Naoto Kasahara,et al. Proposals of Guidelines for High Temperature Structural Design of Fast Reactor Vessels , 2010 .
[10] Farrokh Najmabadi,et al. Fusion materials science and technology research opportunities now and during the ITER era , 2014 .
[11] Mark S. Tillack,et al. Ratcheting Models for Fusion Component Design , 2011 .
[12] Robert W. Conn,et al. Measurements of erosion mechanisms from solid and liquid materials in PISCES-B , 2001 .
[13] Michela Gelfusa,et al. Numerical study of air jet flow field during a loss of vacuum , 2014 .
[14] Dennis G. Whyte,et al. Tritium recovery in ITER by radiative plasma terminations , 2004 .
[15] Ermile Gaganidze,et al. Powder metallurgical processing of self-passivating tungsten alloys for fusion first wall application , 2013 .
[16] D. J. Campbell,et al. Experimental comparison of carbon and beryllium as divertor target materials in JET , 1997 .
[17] David A. Petti,et al. ITER Safety: Lessons Learned for the Future , 1998 .
[18] Kiyoshi Shibanuma,et al. Rail deployment and storage procedure and test for ITER blanket remote maintenance , 2003 .
[19] A. Litnovsky,et al. Dust remobilization in fusion plasmas under steady state conditions , 2015, 1508.06156.
[20] C. H. Skinner,et al. Plasma{material interactions in current tokamaks and their implications for next step fusion reactors , 2001 .
[21] David A. Petti,et al. An overview of safety and environmental considerations in the selection of materials for fusion facilities , 1996 .
[22] Maria Teresa Porfiri,et al. Operating experiences from existing fusion facilities in view of ITER safety and reliability , 2010 .
[23] J. Raeder,et al. LOCA, LOFA and LOVA analyses pertaining to NET/ITER safety design guidance , 1991 .
[24] Mikhail A. Sokolov,et al. Recent progress toward development of reduced activation ferritic/martensitic steels for fusion structural applications , 2009 .
[25] P. Sardain,et al. Power plant conceptual studies in Europe , 2007 .
[26] Zhidan Sun,et al. Dynamic embrittlement at intermediate temperature in a Cu–Ni–Si alloy , 2008 .
[27] Maria Teresa Porfiri,et al. STARDUST experimental campaign and numerical simulations: influence of obstacles and temperature on dust resuspension in a vacuum vessel under LOVA , 2011 .
[28] J. Winter,et al. Dust: A new challenge in nuclear fusion research? , 2000 .
[29] G. Kalinin,et al. ITER structural design criteria and their extension to advanced reactor blankets , 2000 .
[30] Wolfgang J. Choyke,et al. Ion irradiation effects on high strength, high conductivity copper alloys☆ , 1986 .
[31] T. A. Gabriel,et al. R&D for the Spallation Neutron Source mercury target , 2001 .
[32] H. Bolt,et al. Self passivating W-based alloys as plasma facing material for nuclear fusion , 2007 .
[33] Mohamed A. Abdou,et al. Breeding Blanket Modules testing in ITER: An international program on the way to DEMO , 2006 .
[34] G. E. Lucas,et al. Review of small specimen test techniques for irradiation testing , 1990 .
[35] M. Mayer,et al. Codeposition of deuterium with BeO at elevated temperatures , 1997 .
[36] R. M. Boothby,et al. Radiation Effects in Nickel-Based Alloys , 2020, Comprehensive Nuclear Materials.
[37] Andrea Saltelli,et al. An effective screening design for sensitivity analysis of large models , 2007, Environ. Model. Softw..
[38] H.-S. Bosch,et al. Scrape-off layer radiation and heat load to the ASDEX Upgrade LYRA divertor , 1999 .
[39] A. Loarte,et al. A new look at JET operation with Be as plasma facing material , 2005 .
[40] Chihiro Watanabe,et al. Precipitation Processes in a Cu-0.9 mass% Be Single Crystal , 2006 .
[41] Shuichi Takamura,et al. Chapter 4: Power and particle control , 2007 .
[42] G. Janeschitz. Plasma–wall interaction issues in ITER , 2001 .
[43] Wataru Sakaguchi,et al. Formation process of tungsten nanostructure by the exposure to helium plasma under fusion relevant plasma conditions , 2009 .
[44] Panagiotis J. Karditsas. Design issues and implications for structural integrity of fusion power plant components , 2009 .
[45] B. Schweer,et al. Flux dependence of carbon chemical erosion by deuterium ions , 2004 .
[46] J. Roth,et al. Plasma facing and high heat flux materials-needs for ITER and beyond , 2002 .
[47] S. Zinkle. Overview of fusion reactor environment : radiation damage issues , 2004 .
[48] Steven J. Zinkle,et al. Critical questions in materials science and engineering for successful development of fusion power , 2007 .
[49] P. T. Bonoli,et al. First results from Alcator‐C‐MOD* , 1994 .
[50] K. Borrass,et al. Studies of giant ELM interaction with the divertor target in JET , 1997 .
[51] R. J. Pawelko,et al. Tokamak Dust Particle Size and Surface Area Measurement , 1998 .
[52] J. Stober,et al. Ten years of W programme in ASDEX Upgrade—challenges and conclusions , 2009 .
[53] David S. Gelles,et al. Progress and critical issues of reduced activation ferritic/martensitic steel development , 2000 .
[54] Wallace B. Whiting,et al. Effect of uncertainties in thermodynamic data and model parameters on calculated process performance , 1993 .
[55] P. W. Humrickhouse,et al. Dust mobilization studies in the TDMX facility , 2006 .
[56] Christian Grisolia,et al. Resuspension of carbon dust collected in Tore Supra and exposed to turbulent airflow: Controlled experiments and comparison with model , 2014 .
[57] Jochen Linke,et al. Thermal Spray Coatings for Fusion Applications—Review , 2007 .
[58] Joachim Roth,et al. Recent analysis of key plasma wall interactions issues for ITER , 2009 .
[59] T. Yamamoto,et al. 1.06 – The Effects of Helium in Irradiated Structural Alloys , 2012 .
[60] David E. Laughlin,et al. The sequence of precipitation in Cu-2w/0 Be alloys , 1980 .
[61] Jet Team,et al. Results of JET operation with beryllium , 1990 .
[62] A. Murari,et al. First Experimental Campaign to Demonstrate STARDUST-Upgrade Facility Diagnostics Capability to Investigate LOVA Conditions , 2015 .
[63] Steven J. Zinkle,et al. Advanced materials for fusion technology , 2005 .
[64] Gerald L. Kulcinski,et al. The response of polycrystalline tungsten to 30 keV helium ion implantation at normal incidence and high temperatures , 2012 .
[65] Jean-Baptiste Izard. Development of Remote Handling Technologies Tolerant to Operation Ready Fusion Reactor Conditions , 2013 .
[66] Vincent Laporte,et al. Intermediate temperature embrittlement of copper alloys , 2009 .
[67] K. R. Solvason,et al. Natural convection through rectangular openings in partitions—1: Vertical partitions , 1962 .
[68] Huijun Li,et al. Recent progress in research on tungsten materials for nuclear fusion applications in Europe , 2013 .
[69] Michela Gelfusa,et al. Simulations and Experiments to Reach Numerical Multiphase Informations for Security Analysis on Large Volume Vacuum Systems Like Tokamaks , 2015 .
[70] Gerald Pintsuk,et al. Cracking failure study of ITER-reference tungsten grade under single pulse thermal shock loads at elevated temperatures , 2009 .
[71] Steven J. Zinkle,et al. Materials needs for fusion, Generation IV fission reactors and spallation neutron sources – similarities and differences , 2004 .
[72] Michael Rieth,et al. Influence of microstructure and notch fabrication on impact bending properties of tungsten materials , 2010 .
[73] S. Chiocchio,et al. Plasma wall interactions in ITER , 1997 .
[74] Kazuyuki Takase,et al. Effects of Breach Area and Length to Exchange Flow Rates Under the Lova Condition in a Fusion Reactor , 1996 .
[75] Farrokh Najmabadi,et al. Review of blanket designs for advanced fusion reactors , 2008 .
[76] Maria Teresa Porfiri,et al. Loss of vacuum accident (LOVA): Comparison of computational fluid dynamics (CFD) flow velocities against experimental data for the model validation , 2011 .
[77] S. Fabritsiev,et al. The effect of neutron irradiation on the electrical resistivity of high-strength copper alloys , 1997 .
[78] Kazuyuki Takase. Three-Dimensional Numerical Simulations of Dust Mobilization and Air Ingress Characteristics in a Fusion Reactor during a LOVA event , 2001 .
[79] A. Murari,et al. First 3D numerical simulations validated with experimental measurements during a LOVA reproduction inside the new facility STARDUST-Upgrade , 2015 .
[80] A. Becoulet,et al. Efficiency and availability driven R&D issues for DEMO , 2009 .
[81] David A. Petti,et al. A Review of Dust in Fusion Devices: Implications for Safety and Operational Performance , 2002 .
[82] M. L. Apicella,et al. Effects of wall boron coating on FTU plasma operations , 2003 .
[83] Rene Moreau,et al. Eurofer corrosion by the flow of the eutectic alloy Pb–Li in the presence of a strong magnetic field , 2011 .
[84] E.M.J. Komen,et al. SEAFP, Safety and Environmental Assessment of Fusion Power, Final Report , 1995 .
[85] R Toschi,et al. Nuclear fusion, an energy source , 1997 .
[86] R. C. MacDonald,et al. Valuation of Supplemental and Enhanced Oil Recovery Projects With Risk Analysis , 1986 .
[87] A. T. Peacock,et al. Dust and flakes in the JET MkIIa divertor, analysis and results , 1999 .
[88] J. Kittel,et al. History of Fast-reactor Fuel Development , 1993 .
[89] Kazuyuki Takase,et al. Experimental study on buoyancy-driven exchange flows through breaches of a tokamak vacuum vessel in a fusion reactor under the loss-of-vacuum-event condition , 1997 .
[90] Louis K. Mansur,et al. Perspectives on radiation effects in nickel-base alloys for applications in advanced reactors , 2009 .
[91] Yican Wu,et al. Status of R&D activities on materials for fusion power reactors , 2007 .
[92] Pasquale Gaudio,et al. X-ray High-resolution Spectroscopy for Laser-produced Plasma , 2015 .
[93] R. Causey,et al. Beryllium-tungsten mixed-material interactions , 2005 .
[94] Gerald Pintsuk,et al. Damage structure in divertor armor materials exposed to multiple ITER relevant ELM loads , 2009 .
[95] S. Lindig,et al. Self-passivating bulk tungsten-based alloys manufactured by powder metallurgy , 2011 .
[96] Steven J. Zinkle,et al. Scientific and engineering advances from fusion materials R&D , 2002 .
[97] Maria Teresa Porfiri,et al. Large eddy simulation of Loss of Vacuum Accident in STARDUST facility , 2013 .
[98] D. Cacuci,et al. A Comparative Review of Sensitivity and Uncertainty Analysis of Large-Scale Systems—II: Statistical Methods , 2004 .
[99] Marek J. Rubel,et al. Operation of TEXTOR-94 with tungsten poloidal main limiters , 2001 .
[100] S. Zinkle,et al. Operating temperature windows for fusion reactor structural materials , 2000 .
[101] Tamara G. Kolda,et al. Optimization by Direct Search: New Perspectives on Some Classical and Modern Methods , 2003, SIAM Rev..
[102] David A. Petti,et al. The safety implications of tokamak dust size and surface area , 1998 .
[103] T. Kondo,et al. International strategy for fusion materials development , 2000 .
[104] E. E. Bloom. The challenge of developing structural materials for fusion power systems , 1998 .
[105] W. Fundamenski,et al. Transient heat loads in current fusion experiments, extrapolation to ITER and consequences for its operation , 2007 .
[106] C. Ferro,et al. Optimization of the FTU toroidal limiter shape , 1992 .
[107] David R. Smith,et al. A study of molybdenum influxes and transport in Alcator C-Mod , 2001 .
[108] R. W. Conn. Report of the DOE panel on low activation materials for fusion applications , 1983 .
[109] D Di Giovanni,et al. Design of a new experimental facility to reproduce LOVA and LOCA consequences on dust resuspension , 2015 .
[110] Jon C. Helton,et al. Survey of sampling-based methods for uncertainty and sensitivity analysis , 2006, Reliab. Eng. Syst. Saf..
[111] Tetsuo Tanabe,et al. Tritium issues to be solved for establishment of a fusion reactor , 2012 .
[112] F Conetta,et al. Dust tracking techniques applied to the STARDUST facility: First results , 2014 .
[113] P. Sardain,et al. Divertor conceptual designs for a fusion power plant , 2008 .
[114] Michela Gelfusa,et al. Safety Analysis in Large Volume Vacuum Systems Like Tokamak: Experiments and Numerical Simulation to Analyze Vacuum Ruptures Consequences , 2014 .
[115] Jon C. Helton,et al. Uncertainty and sensitivity analysis techniques for use in performance assessment for radioactive waste disposal , 1993 .
[116] Akira Kohyama,et al. Current status and future R&D for reduced-activation ferritic/martensitic steels , 1998 .
[117] Xie Guoliang,et al. The precipitation behavior and strengthening of a Cu–2.0 wt% Be alloy , 2012 .
[118] Max D. Morris,et al. Factorial sampling plans for preliminary computational experiments , 1991 .
[119] Louis K. Mansur,et al. Materials research and development for the spallation neutron source mercury target , 2003 .
[120] Julien Fuchs,et al. Impurity behaviour in the ASDEX Upgrade divertor tokamak with large area tungsten walls , 2002 .
[121] F. J. Davis,et al. Illustration of Sampling‐Based Methods for Uncertainty and Sensitivity Analysis , 2002, Risk analysis : an official publication of the Society for Risk Analysis.
[122] Nikolay Ivanov Kolev,et al. Uncertainty and sensitivity analysis of a postexperiment simulation of nonexplosive melt-water interaction , 1996 .
[123] G. Robert Odette,et al. On the effects of irradiation and helium on the yield stress changes and hardening and non-hardening embrittlement of ∼8Cr tempered martensitic steels : Compilation and analysis of existing data , 2006 .
[124] Reinhard Pippan,et al. Review on the EFDA programme on tungsten materials technology and science , 2011 .
[125] F. Rau,et al. Stellarators - Report on the Ninth International Workshop on Stellarators, held at the Max-Planck-Institut für Plasmaphysik, Garching, Germany, 10 - 14 May 1993 , 1994 .
[126] T. Muroga,et al. Multimodal options for materials research to advance the basis for fusion energy in the ITER era , 2013 .
[127] Alfredo Portone,et al. ITER operating limit definition criteria , 2009 .
[128] M. Rubel,et al. Fusion Reactor Materials and Components: Issues Related to Radioactivity and Radiation-Induced Effects , 2004 .
[129] Akihiko Shimizu,et al. Dust mobilization by high-speed vapor flow under LOVA , 2006 .
[130] Hansoo Lee,et al. Corrosion behavior of plasma-sprayed Al2O3-Cr2O3 coatings in hot lithium molten salt , 2010 .
[131] Michela Gelfusa,et al. Shadowgraph Technique Applied to STARDUST Facility for Dust Tracking: First Results , 2015 .
[132] M. G. Marietta,et al. Uncertainty and sensitivity analysis results obtained in the 1992 performance assessment for the waste isolation pilot plant , 1996 .
[133] Maria Teresa Porfiri,et al. Validation of a loss of vacuum accident (LOVA) Computational Fluid Dynamics (CFD) model , 2011 .
[134] Steven J. Zinkle,et al. Evaluation of high strength, high conductivity CuNiBe alloys for fusion energy applications , 2014 .
[135] David A. Petti,et al. Analyses of loss of vacuum accident (LOVA) in ITER , 2000 .
[136] William R. Wampler,et al. Hydrogen isotope retention in beryllium for tokamak plasma-facing applications , 1999 .
[137] W. Kühnlein,et al. Vacuum plasma-sprayed tungsten on EUROFER and 316L: Results of characterisation and thermal loading tests , 2005 .
[138] Sandro Paci,et al. Dust Mobilization Experiments in the Context of the Fusion Plants - STARDUST Facility , 2006 .
[139] Jonathan Peter Merrison,et al. First experimental results of particle re-suspension in a low pressure wind tunnel applied to the issue of dust in fusion reactors , 2015 .
[140] Manabu Satou,et al. Microstructural development and radiation hardening of neutron irradiated Mo–Re alloys , 2004 .
[141] R. J. Pawelko,et al. Characterization and analysis of dusts produced in three experimental tokamaks: TFTR, DIII-D, and Alcator C-Mod , 2000 .
[142] Michael Finkenthal,et al. Intrinsic molybdenum impurity density and radiative power losses with their scalings in ohmically and ICRF heated Alcator C-Mod and FTU tokamak plasmas , 1999 .
[143] S. Zinkle,et al. The effect of neutron spectrum on the mechanical and physical properties of pure copper and copper alloys , 1996 .
[144] R. Causey,et al. Hydrogen isotope retention and recycling in fusion reactor plasma-facing components , 2002 .