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Nuclear Power Deployment Operation and Sustainability Part 4

Tham khảo tài liệu 'nuclear power deployment operation and sustainability part 4', kỹ thuật - công nghệ, cơ khí - chế tạo máy phục vụ nhu cầu học tập, nghiên cứu và làm việc hiệu quả | Characteristic Evaluation and Scenario Study on Fast Reactor Cycle in Japan 95 Each facility Availability factor Nuclear material quantity and composition Amount of waste generation Capital cost Operation cost Nuclear fleet Sustainability Indices Economics Indices Nat. U Con- . version. Recovered U SWU Composition of Impurities Enrichment NF Composition Material Flows SF Cooling Time Interim Reactor cessin Maximum Enrichment Recovered U Recovered Pu Waste Fabrication Conditions SF Cooling Time Receiving Condition Constraints 1 Constraints Mass-flow Reprocessing Plant Capacity T ransition Rate to Waste Waste Waste G tProcessin lStorage Waste Generation Period Temperature Disposal Fig. 3. Nuclear supply chain and SCM code Figure 3 shows the relationship between the facilities in nuclear fleet. For example the effects from the differences of breeding ratio of FR reprocessing plant and Am-Cm recycling on characteristics from developmental targets influences the material flow from reprocessing plant. With the object oriented design feature and mechanism that conveys information and materials via the interface among highly independent facilities it is easy to place improvements on a facility by itself according to needs. Furthermore the SCM code enabled us to simulate nuclear fuel cycle overall in the process of procurement dispose and transportation of material from the upper to lower facilities without any major change with facility data that indicates basic characteristics of nuclear facilities according to the provided schemes and scenarios as the assumption of analyses by user in timely manners. 3. Characteristics evaluation of equilibrium FR cycle and scenario evaluation In this section evaluation on Japanese nuclear fleet in FaCT project is described mainly by SCM code code. It covers almost all the facilities in Japan from the beginning of the nuclear energy utilization and FR cycle equilibrium state in far future. 3.1 Characteristics evaluation of equilibrium FR