Filters
Results 1 - 1 of 1
Results 1 - 1 of 1.
Search took: 0.016 seconds
[en] The paper presents the most important development in industrial countries for replacement of HEU a top security nuclear material to LEU in research reactor. French development process of U-Mo spent fuel reprocessing give alternative solution on back-end cycle. U-Mo dispersion fuel, which is potential to be loaded as high as 9 g-U/cm3, is candidate for substitution of LEU silicide and all HEU fuel. KAERI has finished a PIE of first full sized fuel rod of U-Mo, which is irradiated to 26 FPD, with 107 W/cm maximum power generation. The PIE results have been incorporate to the new fuel designs of second generation. The 2nd generation test fuel has been fabricated and loaded in to HANARO reactor. The irradiation is planned to finish in the end of 2004. The French U-Mo Group program has already produced significant technical issues based on the fabrication of full sized fuel plates and various irradiation experiments. The irradiation of first 3 full-sized fuel plates of U-Mo with 7 - 9% Mo and density up to 8 gU/cm3 reached 67.5% burnup. The PIE of the fuel irradiated with power of 136 W/cm2 and cladding temperature of 72 oC shows a good performance. U-Mo fuel plate modeling using code developed by ANL-French group and Argentine shows a good comparison to the experimental results. USA is developing process fabrication of monolithic U-Mo fuel. KAERI developing a new process for U and U-Mo foil production. Qualification program of full-sized U-Mo of developer country is planned according to conditions of each country to achieved 50% and 70% burnup and PIE will finish in 2005-2006. France is advanced in plate type fuel fabrication and U-Mo reprocessing beside of irradiation testing and PIE. Korea is advanced in rod type fuel design - fabrication, U-Mo atomization and foil and U-Mo monolithic tube. Argentine is developing HMD for U-Mo powder, U-Mo modeling and fuel plate fabrication. For present 3 year the qualification activities will be dominated by irradiation of full-sized fuel to reach burnup to 50% and 70% and related PIE. If this program results as hoped, the U-Mo fuel which is reprocessable will ready for LEU Silicide and all HEU fuel and an alternative for termination of FRRSNF acceptance program. (author)
Source
Indro Yuwono (ed.) (National Nuclear Energy Agency, Serpong (Indonesia)); Nababan, Binsar (ed.) (National Institute of Sciences, Jakarta (Indonesia)); Suharyanta (ed.) (Nuclear Energy Regulatory Agency, Jakarta (Indonesia)); Centre for Nuclear Materials Security Technology, National Nuclear Energy Agency, Serpong (Indonesia); 107 p; ISSN 1412-2812; 
; Nov 2004; p. 73-83; 5. Seminar on Technology of Nuclear Materials Safety; Seminar Teknologi Pengamanan Bahan Nuklir ke 5; Jakarta (Indonesia); 29 Sep 2004; Also available from Center for Development of Nuclear Informatics, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 17 refs.; 4 tabs.; 2 figs.
; Nov 2004; p. 73-83; 5. Seminar on Technology of Nuclear Materials Safety; Seminar Teknologi Pengamanan Bahan Nuklir ke 5; Jakarta (Indonesia); 29 Sep 2004; Also available from Center for Development of Nuclear Informatics, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 17 refs.; 4 tabs.; 2 figs.