Comparison of the deuterium--tritium neutron wall load distributions in several tokamak fusion reactor designs
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 percent above nominal for the circular case, 43 percent for the PRD, and 12 percent 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.
- Research Organization:
- Princeton Univ., NJ
- OSTI ID:
- 7140805
- Journal Information:
- Nucl. Technol.; (United States), Vol. 31:1
- Country of Publication:
- United States
- Language:
- English
Similar Records
UWMAK-III, a noncircular tokamak power reactor design
UWMAK-III, a noncircular tokamak power reactor design
Related Subjects
THERMONUCLEAR REACTOR WALLS
WALL LOADING
TOKAMAK TYPE REACTORS
ANGULAR DISTRIBUTION
COMPARATIVE EVALUATIONS
DEUTERIUM
FIRST WALL
NEUTRON FLUX
NEUTRON REACTIONS
NUMERICAL SOLUTION
TRITIUM
BARYON REACTIONS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
DISTRIBUTION
HADRON REACTIONS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
POWER DENSITY
RADIATION FLUX
RADIOISOTOPES
STABLE ISOTOPES
THERMONUCLEAR REACTORS
YEARS LIVING RADIOISOTOPES
700201* - Fusion Power Plant Technology- Blanket Engineering