On the implementation of new technology modules for fusion reactor systems codes

Abstract In the frame of the pre-conceptual design of the next generation fusion power plant (DEMO), systems codes are being used from nearly 20 years. In such computational tools the main reactor components (e.g. plasma, blanket, magnets, etc.) are integrated in a unique computational algorithm and simulated by means of rather simplified mathematical models (e.g. steady state and zero dimensional models). The systems code tries to identify the main design parameters (e.g. major radius, net electrical power, toroidal field) and to make the reactor's requirements and constraints to be simultaneously accomplished. In fusion applications, requirements and constraints can be either of physics or technology kind. Concerning the latest category, at Karlsruhe Institute of Technology a new modelling activity has been recently launched aiming to develop improved models focusing on the main technology areas, such as neutronics, thermal-hydraulics, electromagnetics, structural mechanics, fuel cycle and vacuum systems. These activities started by developing: (1) a geometry model for the definition of poloidal profiles for the main reactors components, (2) a blanket model based on neutronics analyses and (3) a toroidal field coil model based on electromagnetic analysis, firstly focusing on the stresses calculations. The objective of this paper is therefore to give a short outline of these models.

[1]  Ulrich Fischer,et al.  Neutronic analyses of the HCPB DEMO reactor using a consistent integral approach , 2014 .

[2]  Bong Guen Hong,et al.  Development of a tokamak reactor system code and its application for concept development of a demo reactor , 2008 .

[3]  Jean-Charles Jaboulay,et al.  Neutronic predesign tool for fusion power reactors system assessment , 2013 .

[4]  Farrokh Najmabadi,et al.  An advanced computational algorithm for systems analysis of tokamak power plants , 2010 .

[5]  H. Tsige-Tamirat,et al.  Neutronics Design Analyses of Fusion Power Reactors Based on a Novel Integral Approach , 2009 .

[6]  Andrej Trkov,et al.  FENDL-2.1, Update of an evaluated nuclear data library for fusion applications , 2004 .

[7]  Rosaria Villari,et al.  Tokamak D-T neutron source models for different plasma physics confinement modes , 2012 .

[8]  Ulrich Fischer,et al.  Neutronic design issues of the WCLL and HCPB power plant models , 2003 .

[9]  P. Hertout,et al.  Conceptual design for the superconducting magnet system of a pulsed DEMO reactor , 2013 .

[10]  M. Sawan,et al.  Self-shielding effects in a tungsten layer in a fusion device , 1999 .

[11]  Frédéric Hecht,et al.  New development in freefem++ , 2012, J. Num. Math..

[12]  S. J. Sackett.  Calculation of electromagnetic fields and forces in coil systems of arbitrary geometry , 1975 .

[13]  K. Hesch,et al.  Conceptual Design of a Toroidal Field Coil for a Fusion Power Plant Using High Temperature Superconductors , 2014, IEEE Transactions on Applied Superconductivity.

[14]  H. Bosch,et al.  ERRATUM: Improved formulas for fusion cross-sections and thermal reactivities , 1992 .

[15]  G. V. Sheffield,et al.  Large Superconducting Magnet Designs for Fusion Reactors , 1971 .

[16]  L. Zani,et al.  Conceptual integrated approach for the magnet system of a tokamak reactor , 2014 .