Safety Assessment of the ARIES Compact Stellarator Design

Abstract ARIES-CS is a 1000 MW(electric) compact stellarator conceptual fusion power plant design. This power plant design contains many innovative features to improve the physics, engineering, and safety performance of the stellarator concept. ARIES-CS utilizes a dual-cooled lead lithium blanket that employs low-activation ferritic steel as a structural material, with the first wall cooled by helium and the breeding zone self-cooled by flowing lead lithium. In this paper we examine the safety and environmental performance of ARIES-CS by reporting radiological inventories, decay heat, and radioactive waste management options and by examining the response of ARIES-CS to accident conditions. These accidents include conventional loss of coolant and loss of flow events, an ex-vessel loss of coolant event, and an in-vessel loss of coolant with bypass event that mobilizes in-vessel radioactive inventories (e.g., tritium and erosion dust from plasma-facing components). Our analyses demonstrate that the decay heat can be safely removed from ARIES-CS and the facility can meet the no-evacuation requirement.

[1]  Laila A. El-Guebaly,et al.  The feasibility of recycling and clearance of active materials from fusion power plants , 2007 .

[2]  David A. Petti,et al.  The Safety and Tritium Applied Research (STAR) Facility: Status-2004 , 2004 .

[3]  Farrokh Najmabadi,et al.  Designing ARIES-CS Compact Radial Build and Nuclear System: Neutronics, Shielding, and Activation , 2008 .

[4]  E. Ruckenstein On solid—liquid mass transfer in turbulent pipe flow , 1967 .

[5]  L. C. Cadwallader,et al.  Safety in the Design of Three Burning Plasma Experiments , 2003 .

[6]  A. W. Shiver,et al.  VANESA: a mechanistic model of radionuclide release and aerosol generation during core debris interactions with concrete , 1986 .

[7]  O. Ogorodnikova,et al.  Tritium permeation through the first wall of the EU-HCPB blanket , 2000 .

[8]  Michael L. Corradini,et al.  Lithium alloy chemical reactivity with reactor materials: current state of knowledge , 1991 .

[9]  David A. Petti,et al.  Re-evaluation of the use of low activation materials in waste management strategies for fusion , 2000 .

[10]  P. Harriott,et al.  Solid-liquid mass transfer in turbulent pipe flow , 1965 .

[11]  Laila A. El-Guebaly,et al.  Recent accomplishments and future directions in the US Fusion Safety and Environmental Program , 2007 .

[12]  Lee C. Cadwallader,et al.  Safety assessment of two advanced ferritic steel molten salt blanket design concepts , 2004 .

[13]  David A. Petti,et al.  A Review of Dust in Fusion Devices: Implications for Safety and Operational Performance , 2002 .

[14]  Takayuki Terai,et al.  JUPITER-II molten salt flibe research : An update on tritium, mobilization and redox chemistry experiments , 2005 .

[15]  Richard F. Mattas,et al.  Comparison of lithium and the eutectic lead lithium alloy, two candidate liquid metal breeder materials for self-cooled blankets , 1995 .

[16]  Farrokh Najmabadi,et al.  Major integration issues in evolving the configuration design space for the ARIES-CS compact stellarator power plant , 2006 .

[17]  Laila A. El-Guebaly,et al.  Systems Studies and Optimization of the ARIES-CS Power Plant , 2008 .

[18]  Richard H. Olsher,et al.  RADIOLOGICAL ASSESSMENTS FOR CLEARANCE OF MATERIALS FROM NUCLEAR FACILITIES , 2003 .

[19]  L.C. Cadwallader,et al.  Reliability Estimates for Power Supplies , 2005, 21st IEEE/NPS Symposium on Fusion Engineering SOFE 05.

[20]  Laila A. El-Guebaly,et al.  Clearance considerations for slightly-irradiated components of fusion power plants , 2007 .

[21]  Steve Fetter,et al.  Long-term radioactive waste from fusion reactors: Part II , 1990 .

[22]  D. Grant,et al.  Hydrogen in 316 steel — diffusion, permeation and surface reaction , 1988 .

[23]  E. Serra,et al.  Influence of the surface conditions on permeation in the deuterium–MANET system , 1997 .

[24]  Laila A. El-Guebaly,et al.  Evaluation of disposal, recycling and clearance scenarios for managing ARIES radwaste after plant decommissioning , 2007 .

[25]  David A. Petti,et al.  Radiological Dose Calculations for Fusion Facilities , 2003 .

[26]  A. R. Raffray,et al.  Engineering Design and Analysis of the ARIES-CS Power Plant , 2008 .

[27]  David A. Petti,et al.  Status of Safety and Environmental Activities in the U.S. Fusion Program , 2004 .

[28]  Lee C. Cadwallader,et al.  Component failure rate data base for fusion applications , 2000 .

[29]  Mark S. Tillack,et al.  Fusion power core engineering for the ARIES-ST power plant , 2003 .

[30]  Laila A. El-Guebaly,et al.  Evolution of Clearance Standards and Implications for Radwaste Management of Fusion Power Plants , 2006 .

[31]  P. Wilsonb,et al.  ARIES-AT safety design and analysis , 2006 .

[32]  Paul P. H. Wilson ALARA: Analytic and Laplacian adaptive radioactivity analysis , 1999 .

[33]  G. R. Smolik,et al.  A summary and assessment of oxidation driven volatility experiments at the INEL and their application to fusion reactor safety assessments , 1994 .

[34]  A. R. Raffray,et al.  ARIES-CS Magnet Conductor and Structure Evaluation , 2008 .

[35]  David Ward,et al.  Conceptual design of the dual-coolant blanket within the framework of the EU power plant conceptual study (TW2-TRP-PPCS12). Final report , 2003 .

[36]  David A. Petti,et al.  Modifications to the MELCOR code for application in fusion accident analyses , 2000 .

[37]  F. Reiter,et al.  Solubility and diffusivity of hydrogen isotopes in liquid Pb17Li , 1991 .

[38]  O. Schipakin,et al.  Experimental study of 210Po release from 17Li83Pb eutectic , 1995 .

[39]  L.C. Cadwallader,et al.  Reliability estimates for oxygen monitors , 2003, 20th IEEE/NPSS Symposium onFusion Engineering, 2003..

[40]  Mark S. Tillack,et al.  ARIES-RS safety design and analysis , 1997 .

[41]  T. Terai,et al.  Diffusion coefficient of tritium in molten lithium-lead alloy (Li17Pb83) under neutron irradiation at elevated temperatures , 1992 .

[42]  Laila A. El-Guebaly,et al.  Activation, Decay Heat, and Waste Disposal Analyses for the ARIES-AT Power Plant , 2001 .

[43]  Laila A. El-Guebaly,et al.  Managing fusion high-level waste—A strategy for burning the long-lived products in fusion devices , 2006 .