S>A fuel cycle analysis of plutonium recycle in a gascooled, graphite- moderated reactor was performed using the fuel cycle code which can be used for IBM 704, 709, or 7090 computer. The fuel cycle variables investigated were three initial uranium enrichments (natural, 1.0, or 1.3 at.%), four plutonium recycle ratios (total, 90%, 75%, or none) and two methods of fuel management (batch irradiation and bidirectional fuel management). Bidirectional fuel management released substantially more energy from a given amount of U/sup 235/ than batch irradiation method. Plutonium recycle not only increased the average burn-up but also improved the peak to average ratio of power density. Poisoning due to Pu/ sup 242/ was less severe than had originally been expected. (auth)