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Abstract

The FURNACE program system performs neutronic and photonic calculations in 3D toroidal geometry for application to fusion reactors. The geometry description is quite general, allowing any torus cross section and any neutron source density distribution for the plasma, as well as simple parametric representations of circular, elliptic and D-shaped tori and plasmas. The numerical method is based on an approximate transport model that produces results with sufficient accuracy for reactor design purposes, at acceptable calculational costs. The report gives a short description of the numerical method, and a user manual for the programs of the system: FURNACE, ANISN-PT, LIBRA, TAPEMA and DRAWER.

Additional information

Authors: VERSCHUUR K A NETHERLANDS ENERGY RESEARCH FOUNDATION, ECN PETTEN (THE NETHERLANDS), NETHERLANDS ENERGY RESEARCH FOUNDATION, ECN PETTEN (THE NETHERLANDS)
Bibliographic Reference: WRITE TO NETHERLANDS ENERGY RESEARCH FOUNDATION ECN, P.O. BOX 1, 1755 ZG PETTEN (THE NETHERLANDS), MENTIONING REPORT ECN-162, 1984
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