The technical issues, development problems and required experiments and facilities for fusion nuclear technology have been investigated. The results have been used to develop a technical framework for a test plan that identifies the role, timing, characteristics and costs of major experiments and facilities. A major feature of this framework is the utilization of non-fusion facilities over the next 15 years, followed by testing in fusion devices beyond about the year 2000. Basic, separate effect and multiple interaction experiments in non-fusion facilities will provide property data, explore phenomena and provide input to theory and analytic modelling. Experiments in fusion facilities can proceed in two phases: (1) concept verification and (2) component reliability growth. Integrated testing imposes certain requirements on fusion testing device parameters; these requirements have been quantified. The nuclear subsystems addressed in the study are: (a) blanket and first wall; (b) tritium processing system; (c) plasma interactive components; and (d) radiation shield. The two generic classes of liquid and solid breeder blankets have significant engineering feasibility issues, and new experimental data must be obtained before selection of an attractive design concept. Liquid metal blanket issues are dominated by problems related to momentum, heat and mass transfer, which can be addressed in non-neutron test facilities. Solid breeder blanket issues are, however, dominated by the effects of radiation, including heating, transmutation and damage, which can be reasonably addressed in fission reactors. The tritium processing uncertainties are primarily related to the control and recovery systems, and most can be addressed in existing and planned non-neutron facilities. A dominant feature of plasma interactive components is the strong interrelation to both plasma physics and nuclear technology. Required facilities include thermomechanical test stands and confinement devices with sufficiently long plasma burn. The radiation shield poses no feasibility issues, but improved accuracy of predictions will reduce design conservatism and lower costs.

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Plateau pressures of the monohydrides of various metals 6 To pressure over dilute solutions of tritium in lithium 7 T 2 pressures above yttrium 9 To pressures above yttrium for various T/Y ratios in the Sieverts' region 10 Equilibrium tritium (T 2) pressures above yttrium (T/Y = 0.001) and lithium (1 wppm T) 11 Flow sheet for blanket tritium systems LIST OF TABLES Title Pm Parameters of a Permeation/Oxidation Tritium Recovery System 13 An Evaluation of Four Methods to Extract Tritium from Liquid Lithium Reference Parameters for the Blanket Tritium System Sources of H into Li 30 Observed Impurities in Operating LHFBRs Observed Impurities in Operating Experimental Lithium Loops Chemical Composition of HT-9 (Sandvik) Typical Impurity Levels of Nonmetallic Elements in Liquid Metal Systems Concentration of Dissolved Metallic Elements in Lithium Activity Levels in Lithium 39 Transfer of Impurities from the Lithium into the Salt 12 iii LIST OF FIGURES