A. "Sagara

Design Group" FFHR

T. Goto

National Institute for Fusion Science (NIFS-Repository)

    On the basis of a steady progress in the LHD experi-ment, a lot of achievements have been made in terms of refinement of the database, physics analysis, and engineer-ing R&D for the helical system. This study advances con-ceptual design activity of the helical DEMO reactor FFHR-d1 by utilizing these achievements and wide-ranged re-searches including the core plasma physics and the reactor technology through cooperative researches in NIFS. This study also aims at establishing an engineering basis that enables engineering demonstration for the helical DEMO and contributing to a progress in nuclear fusion research by clarifying issues and prospects of each research field.  This study has been conducted under the Fusion En-gineering Research Project, launched at the beginning of FY2010. Conceptual design activity for FFHR-d11) and related engineering R&D have been conducted by 3 re-search groups (superconducting magnets, in-vessel compo-nents, reactor system design) that consist of 13 task groups. In this fiscal year, primary design parameters of FFHR-d1 are set. The detailed examination of the core plasma and 3-D design of in-vessel components are in progress.      The design integration task group performed design window analysis based on the direct profile extrapolation (DPE) method2) proposed by the core plasma task group using the system design code HELIOSCOPE. The design point having Rc=15.6m, Bc=4.7T and Pfus=3GW was select-ed as a candidate for FFHR-d13). The feasibility of this de-sign point is validated thorough the detailed analysis by the related task groups: radial-build design by the in-vessel component task group4), evaluation of tritium breeding and neutron shielding performance through neutronics calcula-tions by the blanket task group5), and evaluation of coil cooling performance through thermo-hydraulic calculations by the superconducting magnet and cryogenic system task groups6).  After the decision of the primary design parameters, detailed consideration of the core plasma design is in pro-gress by the core plasma task group in cooperation with the Numerical Experiment Research Project. Calculations of the high-beta equilibrium, neo-classical transport and alpha particle behavior are being performed. The results will be fed back to the LHD experiment. In parallel, detailed con-sideration for a 3-D shape of main components is in pro-gress. A basic shape of in-vessel components (vacuum ves-sel, blanket and divertor plates) is set by the design integra-tion task group using the result of a magnetic field line trac-ing calculation. Neutronics calculations with the 3-D ge-ometry are underway by the blanket task group. Considera-tion for the shape and location of divertor components and exhausting ports is in progress by the in-vessel component task group. In addition, detailed considerations of the de-velopment issues of FFHR-d1 are underway by other task groups including consideration for the shape of heating ports by the heating task group.  Fig. 1.  Design window analysis for FFHR-d1.    Fig. 2. Proposed shape of in-vessel components on the vertically- and horizontally-elongated cross section.   1)  A. Sagara et al., Invited talk on the 10th International Symposium on Fusion Nuclear Technology (ISFNT-10), 11-16 September, 2011, Portland, Oregon, US, O38, to be published in Fusion Eng. Des. (2012). 2)  Miyazawa, J. et al.: Fusion Eng. Des. 86 (2011) 2879. 3)  Goto, T. et al.: Proc. of ITC-21, Toki, Japan, Nov. 28-Dec. 1, 2011, P2-94, to be published in PFR (2012). 4)  Tamura, H. et al.: 21st International Toki Conference (ITC-21), Toki, Japan, Nov. 28-Dec. 1, 2011, P2-23. 5)  Tanaka, T. et al.: 21st International Toki Conference (ITC-21), Toki, Japan, Nov. 28-Dec. 1, 2011, P2-95. 6)  Hamaguchi, S. et al.: 21st International Toki Confer-ence (ITC-21), Toki, Japan, Nov. 28-Dec. 1, 2011, P2-21. 233§1. Conceptual Design Studies towards  LHD-type DEMO ReactorsSagara, A., Goto, T., FFHR Design Group

Conceptual Design Studies towards LHD-type DEMO Reactors

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