[en] The design of eddy current test coils, optimization of eddy current test parameters, reference standard details and eddy current test signal analysis for testing of uranium rod, aluminum clad tubes and cladded fuel element are discussed in details in this paper

[en] The conference brings together experts in different fields like Nuclear Fuel Fabrication involving design manufacture and automation, characterization, quality control and Non destructive testing for sharing their experiences and deliberations. Papers relevant to INIS are indexed separately

[en] This paper deals with thermal analysis of (Th-U)O_2 powders made by co-precipitation process and the results thus obtained are presented

[en] Advanced Fuel Fabrication Facility, BARC Tarapur is engaged in fabrication of MOX fuel elements. Currently MOX fuel elements for PFBR are being fabricated. This paper describes the processes involved in encapsulation and the layout of the equipment's. It also highlights the developments made in the area of automation and process for high productivity and high recovery

[en] There is no real engineering structure which is completely free from flaws. Various non-destructive test (NDT) methods are used for Flaw Characterisation. This includes Detection, Location, Size, Shape, Orientation and Nature of Flaws. Quality of NDT results depends on capability of Test Equipment's, Effectiveness of Test Procedures and competence of personnel. This presentation will cover a review of various aspects related to reliability and effectiveness of NDT. Results of two programmes related to NDT effectiveness, in which authors Lab. has participated, are also discussed

[en] Canada is the largest uranium producing country in the world and Canadian companies are recognized leaders in many aspects of the international uranium industry including exploration, mining, extraction and refining of uranium, uranium fuel manufacturing, and design, construction and operation of nuclear power plants. In the light of a brief historical background, the status of current uranium processing activities in Canada will be reviewed emphasizing advantages Canadian companies enjoy and challenges they face. Key aspects of nuclear fuel cycle from Canadian perspective will be highlighted. (author)

[en] Fast Breeder Test Reactor at Kalpakkam has already achieved 1. 5 GWd/t burn up. The reactor is presently charged with hybrid fuel consisting of uranium, plutonium mixed carbides (MC) of different compositions, densities and uranium-plutonium mixed oxide, (U_0_._5_6, Pu_0_._4_4)O_2. The present paper deals with effect of the non-metallics in the carbide fuels and the methodologies employed in the analysis of the carbides for the respective elements

[en] Effectiveness of any function rests on three engines - technology, systems and people. Characterization and Quality Control of nuclear fuel is no an exception. Systems integrate people and technology. Technology without systems is creative chaos while systems without technology is mindless bureaucracy. People who man should bridge and blend these two proportionately. Systems provide both means and platform for continual improvement of quality. ISO 9001:2008, international standard for Quality Management System based on the eight principles of total quality management has been used as a driver for building and enhancing the quality of fuel fabricated at NFC. This paper brings out how this international standard has been used as a platform to continually upgrade the quality of fuel manufactured at NFC and its performance. Results thus far obtained are also discussed

[en] The demands from nuclear fuels are constantly being enhanced with the growth of nuclear energy programme. New trends in the development of nuclear fuels include increase in burn-up, increase in operating temperature, improving breeding ratio and increase in fissile loading in the fuel. Research on all these aspects of development of nuclear fuels is under progress in BARC - an outline of which will be presented. Various processing techniques which need to be adopted for achieving the special features of nuclear fuels will be briefly discussed and the role quality control has in process control will be illustrated. As fuel behaviour modeling complements the fuel development work, modeling aspects will be briefly covered along with the recent experimental results on fuel behaviour in off normal conditions. (author)

[en] 19 and 37 element natural uranium bundles are used in 220 MWe and 540 MWe PHWRs, respectively. 22-element bundle, using natural uranium as fuel was also developed, manufactured and successfully irradiated in NAPS (a 220 MWe PHWR) reactors. Presently 19 and 37 element natural uranium bundles are used upto 15000 MWD/TeU. Increase in fuel burnup beyond 15000 MWD/TeU using higher fissile content material like slightly enriched uranium in place of natural uranium in 19 and 22-element fuel bundles, used in 220 MWe PHWRs is being investigated. Performance of these fuel bundles at high burnup is analysed in the report