Published November 1998 | Version v1
Journal article

A tritium catalytic fusion reactor concept

  • 1. Institute of Nuclear Fusion, Madrid Polytechnic University, Madrid (Spain)
  • 2. Soreq NRC, Yavne (Israel)
  • 3. ETSI Industriales, UNED, Madrid (Spain)

Description

The performance of deuterium targets with small tritium seeding is analysed. The objective is to take advantage of the features of fusion reactivity ratios for very high burning temperatures in order to minimize tritium needs and to reduce the ignition temperature as much as possible. It is found theoretically and computationally that there is a regime for deuterium-tritium DTx plasmas (with x ∼ 0.03) where the final content of tritium in the pellet debris is the same as the initial contents in the original pellet. No external blankets to breed tritium would thus be needed. Although energy gains are limited because of the small fusion yield of DD reactions, the energy gain of DTx targets is higher than that of pure deuterium plasmas. The ignition temperature and the driver energy are lower than the corresponding values of DD pellets. This concept is also very useful to reduce the tritium inventory and to simplify the complexity of inertial fusion reactors which use stoichiometric DT. (author)

Additional details

Publishing Information

Journal Title
Nuclear Fusion
Journal Volume
38
Journal Issue
11
Journal Page Range
p. 1651-1664
ISSN
0029-5515

Optional Information

Notes
46 refs, 10 figs, 2 tabs