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Additional resources for Advances in Fast Reactor Technology (IAEA TECDOC-1015)

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Subsequent to the preparation of the renewed EFR strategy the role of Superph,nix in relation to the back end of the fuel cycle has been reinforced by the findings of the French Government 46 Commission to evaluate the capacity of the reactor as a research tool (the so-called 'Castaing Commission') which gives its support to the strategy. The on-going programme therefore takes full benefit of the Superph,nix Knowledge Acquisition Programme, addresses the issues that are raised concerning sodium coolant and inspectability, seeks to exploit the flexibility of fast reactors in the fuel cycle and explore innovative concepts for the improvement of the EFR Reference Design.

Various tests and data acquisition operations planned during the operation programme were continued during the 60 % NP steady state. Power was temporarily reduced several times: to 50 % NP in order to conduct the last adjustments to the equipment of the electricity production facilities and to avoid automatic shutdown of the plant in the event of a spurious trip of a turbine. On another occasion, it was reduced to 40 % NP to enable repairing a steam inlet piping support, with the corresponding turbine shut down.

It is characterized by an increase of the fuelled pins number (387 instead of 336) to the detriment of unfuelled pins (82 instead of 133) and by the introduction of a moderator (1 ^l^C) in the unfuelled pins. A 6-batch cycle was modelled and has shown the possibility of suppressing the intermediate mid-cycle shutdown for reactivity control via diluent management. %). However the sodium void worth is rather high and must be reduced in further studies. 2 Mitigation of core-melt accident consequences Analyses, which have been performed to assess the recriticality and core-melt energetics potentials for the CAPRA reference oxide and the Pu w/o U core have shown that compared to a conventional core the risk of recriticality is increased because of the much higher Pu-enrichment.

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Advances in Fast Reactor Technology (IAEA TECDOC-1015)

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