[Table of Contents]

Plasma and Fusion Research

Volume 7, 2405109 (2012)

Regular Articles

Modification of DOHEAT for Optimization of Coolant Conditions in DEMO Blanket
Hiroyasu UTOH, Kenji TOBITA, Youji SOMEYA and Makoto NAKAMURA
Japan Atomic Energy Agency, Rokkasho-mura, Aomori 039-3212, Japan
(Received 9 December 2011 / Accepted 1 May 2012 / Published 26 July 2012)


For optimization of coolant conditions in DEMO blanket design, a two-dimensional (2D) nuclear-thermal-coupled analysis code, DOHEAT, has been modified. A striking feature of DOHEAT is to have a user-friendly interface that enables users to create an appropriate analysis model for different blanket concepts without much diffculty. In the modified DOHEAT, the coolant condition calculation module was added into the 2D thermal analysis module, and the temperature profile in the blanket was provided based on the nuclear heating rate profile and coolant temperature. In addition, numerical solution of simultaneous linear equation is changed from successive over relaxation (SOR) method to bi-conjugate gradient stabilized (Bi-CGStab) method for calculation speed-up. By improving DOHEAT, a series of blanket analysis including not only neutronics and thermal analysis but also coolant condition can be done. The modified DOHEAT allows to calculate the temperature change of the coolant along the cooling tube, and to evaluate the accurate temperature distribution of blanket.


blanket, design, fusion reactor, nuclear analysis, coolant, thermal analysis, DOT3.5

DOI: 10.1585/pfr.7.2405109


  • [1] X-5 Monte Carlo Team, MCNP-A General Monte Carlo N-Particle Transport Code, Version 5, Vol. II, La-CP-03-0245, Los Alamos National Laboratory, 2003.
  • [2] D. Aquaro et al., Fusion Eng. Des. 82, 2226 (2007).
  • [3] M.E. Sawan et al., Fusion Eng. Des. 85, 1027 (2010).
  • [4] W.W. Eng1e, K-1693, Union Carbide Corporation, Computing Techno1ogy Center (1967).
  • [5] H. Kawasaki, JAERI-M91-058 (1991).
  • [6] M. Enoeda et al., Nucl. Fusion 43, 1837 (2003).
  • [7] PPCS overall report (2004).
  • [8] H. Utoh et al., Fusion Eng. Des. 86, 2378 (2011).
  • [9] W.A. Rhoades and F.R. Mynatt, ORNL/RSIC/CCC-276 (1975).
  • [10] K. Maki et al., JAERI-M91-072 (1991).
  • [11] K. Shibata et al., JAERI 1319 (1990).
  • [12] D.L. Aldama and A. Trkov, INDC(NDS)-467, IAEA (2004).
  • [13] H.A. van der Vorst, J. Sci. Stat. Comput. 13, 631 (1992).
  • [14] K. Tobita et al., Fusion Eng. Des. 85, 1342 (2010).
  • [15] C. Liu et al., Fusion Eng. Des. 85, 979 (2010).

This paper may be cited as follows:

Hiroyasu UTOH, Kenji TOBITA, Youji SOMEYA and Makoto NAKAMURA, Plasma Fusion Res. 7, 2405109 (2012).