A Comparison of the Deuterium-Tritium Neutron Wall Load Distributions in Several Tokamak Fusion Reactor Designs
- 1 October 1976
- journal article
- research article
- Published by Taylor & Francis in Nuclear Technology
- Vol. 31 (1) , 32-47
- https://doi.org/10.13182/nt76-a31696
Abstract
Since the tokamak scheme of plasma confinement provides a toroidal source of fusion neutrons,wide variations in the source distribution at the wall surface are possible. A numerical solution of the neutron streaming equation has been applied to the calculation of the flux and current as functions of wall position for a circular cross-section tokamak and two noncircular tokamaks, the Princeton Reference Design (PRD) and the University of Wisconsin UWMAK-I. The results show significant variations in the pattern of the angular flux and substantial peaking in the scalar flux and current. For example, the current peaks at 22% above nominal for the circular case, 43% for the PRD, and 12% for UWMAK-I. The nominal value, total source ÷ total area, is the commonly stated “wall load.” Effects of this magnitude cannot be ignored in future reactor designs when power densities, damage rates, etc., are evaluated.Keywords
This publication has 5 references indexed in Scilit:
- First wall surface problems for a D ↽ T tokamak reactorJournal of Nuclear Materials, 1974
- Particle Release from Niobium Irradiated with 14-MeV NeutronsPhysical Review Letters, 1974
- Neutron flux distribution on the wall of toroidal controlled thermonuclear reactor devices with elongated cross sectionThe European Physical Journal A, 1974
- First-wall erosion in fusion reactorsNuclear Fusion, 1972
- Tokamak EquilibriumPhysics of Fluids, 1971