Fusion Nuclear Science Facility (FNSF) before Upgrade to Component Test Facility (CTF)

Abstract The compact (R0~1.2-1.3m) Fusion Nuclear Science Facility (FNSF) is aimed at providing a fully integrated, continuously driven fusion nuclear environment of copious fusion neutrons. This facility would be used to test, discover, and understand the complex challenges of fusion plasma material interactions, nuclear material interactions, tritium fuel management, and power extraction. Such a facility properly designed would provide, initially at the JET-level plasma pressure (~30%T2) and conditions (e.g., Hot-Ion H-Mode, Q<1)), an outboard fusion neutron flux of 0.25 MW/m2 while requiring a fusion power of ~19 MW. If and when this research is successful, its performance can be extended to 1 MW/m2 and ~76 MW by reaching for twice the JET plasma pressure and Q. High-safety factor q and moderate-plasmas are used to minimize or eliminate plasma-induced disruptions, to deliver reliably a neutron fluence of 1 MW-yr/m2 and a duty factor of 10% presently anticipated for the FNS research. Success of this research will depend on achieving time-efficient installation and replacement of all internal components using remote handling (RH). This in turn requires modular designs for the internal components, including the single-turn toroidal field coil center-post. These device goals would further dictate placement of support structures and vacuum weld seals behind the internal and shielding components. If these goals could be achieved, the FNSF would further provide a ready upgrade path to the Component Test Facility (CTF), which would aim to test, for ≤6 MW-yr/m2 and 30% duty cycle, the demanding fusion nuclear engineering and technologies for DEMO. This FNSF-CTF would thereby complement the ITER Program, and support and help mitigate the risks of an aggressive world fusion DEMO R&D Program. The key physics and technology research needed in the next decade to manage the potential risks of this FNSF are identified.

[1]  E. D. Fredrickson,et al.  A component test facility based on the spherical tokamak , 2005 .

[2]  Toshihide Tsunematsu.  Broader Approach to fusion energy , 2009 .

[3]  A. Polevoi,et al.  Chapter 1: Overview and summary , 2007 .

[4]  S. Zinkle.  Overview of fusion reactor environment : radiation damage issues , 2004 .

[5]  B. Braams,et al.  Plasma Edge Physics with B2‐Eirene , 2006 .

[6]  Roger E. Stoller,et al.  MD description of damage production in displacement cascades in copper and α-iron , 2003 .

[7]  C.P.C. Wong,et al.  Mission and overview of a Fusion Development Facility , 2009, 2009 23rd IEEE/NPSS Symposium on Fusion Engineering.

[8]  E. M. Jones,et al.  Latest JET results in deuterium and deuterium-tritium plasmas , 1997 .

[9]  Hirotaro Mori,et al.  Observation of the One-Dimensional Diffusion of Nanometer-Sized Dislocation Loops , 2007, Science.

[10]  R J Fonck,et al.  Tokamak startup using point-source dc helicity injection. , 2009, Physical review letters.

[11]  D. Whyte.  On the consequences of neutron induced damage for volumetric fuel retention in plasma facing materials , 2009 .

[12]  Masaru Nakamichi,et al.  In-pile tritium permeation through F82H steel with and without a ceramic coating of Cr2O3-SiO2 including CrPO4 , 2007 .

[13]  Alice Ying,et al.  Results of an International Study on a High-Volume Plasma-Based Neutron Source for Fusion Blanket Development , 1996 .

[14]  L. L. Lao,et al.  Physics Basis of a Fusion Development Facility Utilizing the Tokamak Approach , 2010 .

[15]  P. J. Knight,et al.  Conceptual design of a component test facility based on the spherical tokamak , 2008 .

[16]  Evidence of radiation damage impact on material erosion in plasma environment , 2009 .

[17]  Graydon L. Yoder,et al.  Remote Handling and Plasma Conditions to Enable Fusion Nuclear Science R&D Using a Component Testing Facility , 2009 .

[18]  Brian D. Wirth,et al.  Multiscale modeling of radiation damage in Fe-based alloys in the fusion environment , 2004 .

[19]  R. E. Waltz,et al.  Simulations of internal transport barrier formation in tokamak discharges using the GLF23 transport model , 2002 .