[en] The results of three studies sponsored by the Atomic Industrial Forum are summarized. The studies dealt with legal aspects, economic impact, and safeguards considerations of the NRC provisional plan for plutonium recycle. (DG)

No abstract available

[en] A brief overview on the Thorium fuel cycle technology will be described first. Based on the published information, the potential advantages and technical characteristics of the Thorium fuel utilization technologies are described in detail. Special emphasis will be placed on the technological feasibility and maturity of the methods to examine the practicability of their actual implementation in the near future. Then, realistic and possible ways to the deploy of the Thorium fuels utilization are discussed in terms of both value of the implementation and the technological feasibility and practicability. (author)

[en] This paper describes a thorium-fueled PFB blanket concept for a Commercial Tokamak Hybrid Reactor. A preliminary mechanical concept is presented and the results of neutronics, thermal-hydraulics and economics analyses are discussed. Futher work needed to design and advance the concept is recommended

[en] Parametric design and systems analysis for inertial confinement fusion-fission hybrids are presented. These results were generated as part of the Electric Power Research Institute (EPRI) sponsored Feasibility Assessment of Fusion-Fission Hybrids, using an Inertial Confinement Fusion (ICF) hybrid power plant design code developed in conjunction with the feasibility assessment. The SYMECON systems analysis code, developed by Westinghouse, was used to generate economic results for symbiotic electricity generation systems consisting of the hybrid and its client Light Water Reactors (LWRs). These results explore the entire fusion parameter space for uranium fast fission blanket hybrids, thorium fast fission blanket hybrids, and thorium suppressed fission blanket types are discussed, and system sensitivities to design uncertainties are explored

[en] A summary is given of the 1978 status of fuel recycle technology, along with the research and development (R and D) which is required prior to commercialization of fuel recycle. The fuel cycles consider use of uranium, thorium, or mixed uranium--thorium-based fuels; the reactor types include Light Water Reactors (LWRs), Spectral Shift Controlled Reactors (SSCRs), Heavy Water Reactors (HWRs), High-Temperature Gas-Cooled Reactors (HTGRs), Liquid Metal Fast Breeder Reactors (LMFBRs), and Gas-Cooled Fast Reactors (GCFRs). Estimates of the schedules and costs for implementing the various fuel cycles in the different reactor types are given, and include those for demonstration/pilot plants. The technical areas cover fuel fabrication/refabrication, fuel reprocessing, fuel qualification, and waste treatment

No abstract available

[en] The following possibilities are examined for stretching the nuclear fuel supply: (1) fast breeder reactors, (2) thorium cycle, (3) heavy water reactors, (4) better isotope separation, and (5) electronuclear boosting

No abstract available

[en] An assessment of the impact of utilizing the ²³³U/thorium fuel cycle in the U.S. nuclear economy is strongly dependent upon several decisions involving nuclear energy policy. These decisions include: (1) to recycle or not recycle fissile material; (2) if fissile material is recycled, to recycle plutonium, ²³³U, or both; and (3) to deploy or not to deploy advanced reactor designs such as Fast Breeder Reactors (FBR's), High Temperature Gas Reactors (HTGR's), and Canadian Deuterium Uranium Reactors (CANDU's). This report examines the role of thorium in the context of the above policy decisions while focusing special attention on economics and resource utilization