The dense Z pinch as a fusion power reactor: breeding and radiation damage considerations

The DZP offers the possibility of a very compact and simple fusion reactor. As part of a continuing assessment of this potential we present here calculations of the tritium breeding performance of a recently proposed DZP reactor. It is concluded that in a heavy-water cooled and moderated reactor adequate breeding would be readily achieved. The extent to which neutron radiation damage to the high pressure (approx. 10 MPa) containment vessel will determine allowable volumetric power densities is also estimated. It is shown that such considerations will not prevent operation of DZP reactors at volumetric power densities similar to those achieved in current PWRs, and thus two orders of magnitude greater than those of typical proposed tokamaks. (author)