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Reduced Enrichment for Research and Test Reactors
Nuclear Engineering Division at Argonne
U.S. Department of Energy

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Abstracts and Available Papers Presented at the
1999 International RERTR Meeting

SCRAP RECOVERY PROCESS FOR OXIDE FUEL PLATES

By: BG Susanto, Anwar Muchsin, Agus Sartono, Agung Kadaryono, M. Ali Akbar
and BoyBull


PT Batan Teknologi (Persero)
Jakarta - Indonesia.

ABSTRACT

SCRAP RECOVERY PROCESS FOR OXIDE FUEL PLATES.  The existing of  scrap products  in the form oxide fuel plates  is very important  to be recovered and inputted in the process line.  In this paper work, there were 720 scrap of fuel plates (equal to 44,858 grams U)  from fabrication process have been dissolved. From this  recovery  process is obtained 43215.0 grams U in the form dirty oxide fuel powder. Around  27,188.3 grams of U in the form of  oxide fuel powder have been dissolved by HNO3 concentrated. From this dissolution  moreless  23,364 grams U in the form of uranyl nitrate have been obtained temporarily. The extraction and stripping process to obtain the purity of uranyl nitrate also has been done.  From this process the uranium results in the form uranyl nitrate are 17,563.13 grams.  The contents of impurity level of each element also have been compared to the standard limits used in manufacturing the fuel element for research reactors.  The total boron equivalent is 3,083 ppm, which is lower than limit of specification.


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Contact:
Bambang Galung Susanto
PT BATAN Teknologi (Persero)
Kawasan Puspiptek Serpong (15314)
Tangerang, Indonesia

Phone:  62 21 756 3237
Fax:      62 21 756 6646
E-mail:  bgs7560@vision.net.id

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Last modified on July 29, 2008 11:33 +0200