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Additional resources for Advances in Fast Reactor Technology (IAEA TECDOC-1015)
STAGE 2 DISMANTLING OF THE RAPSODIE EXPERIMENTAL FAST REACTOR The RAPSODIE experimental loop type sodium cooled fast reactor went critical for the first time in 1967. This reactor located at CADARACHE was operated by the CEA. The nominal power was increased from 24 MWth to 40 MWth in 1970 after modifications of the core and the systems. Up to the discovery in October 1978 of a very small sodium leak estimated at 10 g/year across the primary vessel, RAPSODIE did not experience any safety problems and provided considerable fuel data (maximum BU 26 %).
The answer will be negative. China will not have enough suitable and, economical conventional resources, except nuclear. It is obviously mat nuclear power in large scale needs fast breeder reactors, which just is the case of China ACKNOWLEDGEMENTS The Author thanks to his colleagues and especially to Mr. Tian Chunjiu, Mr. Hong Sunzhang, Mr. Ma Zhiwing, Mr. Peng Tonguo, Mr. Xie Guangshan, Mrs. Zhang Luxian, Mrs. Liu Lianping, Mr. Lu Xuejun, Miss Zhang Yen for providing the informations in order to prepare this paper.
Results of the exploratory investigations are promising in that an additional medium line of defense might be introduced into CAPRA cores to cope with the recriticality risk. According to the present status of analysis prompt critical conditions cannot be completely excluded, but scenarios with high reactivity ramp rates and energetics are very unlikely. Experimental information on the transient behaviour of CAPRA pins, diluents and pools with inert materials is urgently needed. The proof that inherent features and special measures/devices will work under the various circumstances of a core-melt accidents needs extensive code calculations.
Advances in Fast Reactor Technology (IAEA TECDOC-1015)