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[en] The future program which has been approved by the Federal Government in fall 1974 is based on the following: plutonium recycle at least within the next decade is a necessity. It has been shown that it is technically and economically feasible to introduce well designed plutonium elements in water reactors
[en] The paper is considering the changes in delayed neutron fraction, reactivity coefficients, and control rod reactivity associated with plutonium insertion. Description of fuel assembly and core design, plutonium recycle fuel management and experience of KWU reactors as well as KWU development programme is given (author)
[en] Summary: • Development of the next version of G4ECONS is progressing well; • Comparable results obtained from the benchmarking of G4ECONS, HEEP and H2A for hydrogen production; • Completed benchmarking G4ECONS with NEST in collaboration with IAEA: –Once-through SCWR; – Two fast reactors with closed fuel cycle.
[en] The paper describes the programme of nuclear power growth and plutonium production in Sweden up to 1990. Justification is given for commercial plutonium recycling in thermal power reactors starting in 1980. Review of experimental programme is presented. (author)
[en] The strategy adopted in India is to utilize the plutonium produced in CANDU type reactors in the fast breeders when these become available. In fact, a 40 MW(t) Fast Breeder Reactor is under construction at the Reactor Research Centre near Madras to gain experience with the sodium cooled fast reactors
[en] As the plutonium content in mixed oxide fuels for thermal reactors is relatively small, only limited changes are expected in their behaviour as compared to uranium fuels. This assumption is being confirmed by experiments initiated by BELGONUCLEAIRE ten years ago on mixed oxide fuels, first with stainless steel cladding and later on with Zircaloy cladding. The confidence is continuously being built up through the good behaviour of more than 990 rods irradiated in various power reactors (BR 3, DODEWAARD, GARIGLIANO). About 40 irradiation experiments in the BR 2 reactor were launched to complete our knowledge. (author)
[en] Conclusion: • GIF Cost Estimating Methodology is available for use by all GIF projects. • Training for users is available at varying levels of detail. • The EMWG continues to monitor Methodology applications. • Small scale activities on additional GEN IV related case studies.
[en] Until the present time considerable efforts have already been made in the area of fabrication, utilization and reprocessing of Th-based fuels for different types of reactors, namely: by FRG and USA - for HTRs; FRG and Brazil, Italy - for LWRs; India - for HWRs and FBRs. Basic research of thorium fuels and thorium fuel cycles are also being undertaken by Australia, Canada, China, France, FRG, Romania, USSR and other countries. Main emphasis has been given to the utilization of thorium fuels in once-through nuclear fuel cycles, but in some projects closed thorium-uranium or thorium-plutonium fuel cycles are also considered. The purpose of the Technical Committee on the Utilization of Thorium-Based Nuclear Fuel: Current Status and Perspective was to review the world thorium resources, incentives for further exploration, obtained experience in the utilization of Th-based fuels in different types of reactors, basic research, fabrication and reprocessing of Th-based fuels. As a result of the panel discussion the recommendations on future Agency activities and list of major worldwide activities in the area of Th-based fuel were developed. A separate abstract was prepared for each of the 9 papers in this proceedings series
[en] EMWG - Plans for the future: - Continue improvements to G4ECONS v3.0; - Seek feedback from SSCs using survey questionnaire; - Discuss and agree on further collaboration with IAEA; - Publication of work on benchmarking; - Monitor use of the methodology and seek feedback; - Maintain watch on international activities on nuclear economics.