A highgain fusionfission reactor for producing uranium233
Abstract
The neutronics of several hybrid fissionfusion reactors were analyzed using a computational method based on the ANISN transport code (Engle, 1967) to develop a design capable of producing large quantities of U233 while maintaining a tritium breeding ratio greater than unity. In the optimum design, an equilibrium concentration of Pu239 and U238 replaces thorium in a converter region, significantly increasing the multiplication of 14MeV source neutrons. The tritium and fissile breeding rates of the reactor are 1.052 and 1.880, respectively, and 3.537 U233 nuclei are produced per fusion neutron. The results of two series of timedependent calculations, analyzing the longterm operation of a near optimal hybrid reactor for U233 production and shortterm operation to produce the 30,000 kg of Pu239 required to initiate the longterm process, are presented.
 Publication:

Nuclear Technology
 Pub Date:
 June 1976
 DOI:
 10.13182/NT76A31604
 Bibcode:
 1976NucTe..29..392S
 Keywords:

 Breeder Reactors;
 FusionFission Hybrid Reactors;
 Reactor Design;
 Uranium 233;
 Blankets;
 Economic Analysis;
 Neutrons;
 Plutonium Isotopes;
 Time Dependence;
 Tritium;
 Nuclear and HighEnergy Physics