Advertisement

Development of a method for nuclide leaching from glass fiber in HEPA filter

  • Gye-Nam Kim
  • Suk-Chol Lee
  • Dong-Bin Shon
  • Hye-Min Park
  • Wang-Kyu Choi
  • Jei-Kwon Moon
Article

Abstract

For the disposal of the high efficiency particulate air (HEPA) glass filter to environment, the glass fiber should be leached to lower its radioactive concentration. To derive the optimum method for removal of Co and Cs from HEPA glass fiber, four methods were applied in this study. Results of electrochemical leaching of glass fiber by 4.0 M HNO3–0.1 M Ce(IV) solution showed that the removal efficiency of 134Cs, 137Cs, and 60Cs from glass fiber after 5 h was 96.4, 93.6, and 93.8%, respectively. Results by 5 wt% NaOH solution showed that the removal efficiency of 134Cs, 137Cs, and 60Cs after 30 h was 81.7, 82.1, and 10.0%, respectively. Results by repeat 2.0 M HNO3 solution showed that the removal efficiencies of 134Cs, 137Cs, and 60Cs after 2 h of three repetitions were 96.2, 99.4, and 99.1%, respectively. Finally, results by repeat 4.0 M HNO3 solution showed that the removal efficiencies of 134Cs, 137Cs, and 60Cs after 4 h of three repetitions were 100, 99.9, and 99.9%, respectively, and their radioactivities were below 0.1 Bq/g. Therefore, the chemical leaching method by 4.0 M HNO3 solution was considered as an optimum one for removal of cesium and cobalt from HEPA glass fiber for self disposal. Also the removal efficiencies of 60Co, 134Cs, and 137Cs from the waste-solution after its precipitation-filtration treatment for reuse of 4.0 M HNO3 waste-solution were 88.0, 95.0, and 99.8%.

Keywords

HEPA Glass fiber Chemical leaching Precipitation-filtration 

Notes

Acknowledgment

This work was supported by the Nuclear Research & Development Program of the Korea Science and Engineering Foundation (KOSEF) funded by the South Korean government (MEST).

References

  1. 1.
    Chun YB (2008) Operation of nuclear fuel cycle research facility. Korea Atomic Energy Research Institute, Dajeon. http://www.kornis21.kaeri.re.kr. Accessed 1 Jan 2008
  2. 2.
    Leuze RE, Bond WD, Scheitlin FM (1980) Recovery of plutonium from HEPA filters by Ce(IV)-promoted dissolution of PuO2 and recycle of the cerium promoter. Oak Ridge National Laboratory, Oak Ridge. http://www.osti.gov. Accessed 22 Jul 1980
  3. 3.
    Qureshi ZH, Strege DK (1994) Pilot-scale tests of HEME and HEPA dissolution process. Westinghouse Savannah River Company, Savannah River Technology Center, Aiken. http://www.osti.gov. Accessed Jun 1994
  4. 4.
    Meikrantz DH, Bourne GL, McFee JN, Mex AN, Burdge BG, McConnell JW (1990) Method of recovering hazardous waste from phenolic resin filters. United States Patent 4995916, U.S. Department of Energy, WashingtonGoogle Scholar
  5. 5.
    Argyle MD, Demmer RL, Archibald, KE, Brewer KN, Pierson KA, Shackelford KR, Kline KS (1999) INEEL HEPA filter leach system: a mixed waste solution. Idaho National Engineering and Environmental Laboratory, Idaho falls. http://www.wmsym.org. Accessed 28 Feb 1999
  6. 6.
    Donovan RI, O’Brien BH (1984) NWCF HEPA filter leaching demonstration results. Westinghouse Idaho Nuclear Company, Idaho FallsGoogle Scholar
  7. 7.
    McCray CW, Brewer KN (1992) HEPA filter leach system technical basis report, WINCO-1096, Westinghouse Idaho Nuclear Company, Idaho FallsGoogle Scholar
  8. 8.
    Chakravartty AC (1995) HEPA filter leaching concept validation trials at the idaho chemical processing plant. Idaho national engineering laboratory, Idaho falls. http://www.osti.gov. Accessed Apr 1995
  9. 9.
    Fanning JC (1995) The solubilities of the alkali metal salts and the precipitation of Cs+ from aqueous solution. Coord Chem Rev 149:27–36CrossRefGoogle Scholar
  10. 10.
    Lee E, Lim J, Chung D, Yang H, Kim K (2010) Selective removal of Cs and Re by precipitation in a Na2CO3–H2O2 solution. J Radioanal Nucl Chem 284:387–395CrossRefGoogle Scholar
  11. 11.
    Asano Y, Asanuma N, Ito T, Kataoka M, Fujino S, Yamamura T, Sugiyama W, Tomiyasu H (1997) Study on a nuclear fuel reprocessing system based on the precipitation method in mild aqueous solutions. Nucl Technol 120:198–210Google Scholar
  12. 12.
    Asanuma N, Harada M, Ikeda Y, Tomiyasu H (2001) New approach to nuclear fuel reprocessing in non-acidic aqueous solutions. J Nucl Sci Technol 38(10):866–871CrossRefGoogle Scholar
  13. 13.
    Leddicotte GW (1961) The radiochemistry of rhenium. Oak Ridge National Laboratory, Oak Ridge. http://www.osti.gov. Accessed 1 Jan 1961
  14. 14.
    Rollin S, Spahiu K, Eklund UB (2001) Determination of dissolution rates of spent fuel in carbonate solutions under different redox conditions with a flow-through experiment. J Nucl Mater 297:231–243CrossRefGoogle Scholar
  15. 15.
    Dean JA (1979) Lange’s handbook of chemistry, 12th edn. McGraw-Hill, New YorkGoogle Scholar
  16. 16.
    Dewberry RA, Casella VR, Sigg RA, Salaymeh SR, Moore FS, Pak DJ (2008) Holdup measurements for three visual examination and TRU remediation glovebox facilities at the Savannah River Site. J Radioanal Nucl Chem 275:541–554CrossRefGoogle Scholar
  17. 17.
    Sas D, Sladek P, Janda J (2010) Measuring alpha and beta activity of filter and swab samples with LSC. J Radioanal Nucl Chem 286:513–517CrossRefGoogle Scholar
  18. 18.
    Yasuoka Y, Ishikawa T, Tokonami S, Takahashi H, Sorimachi A, Shingi M (2009) Radon mitigation using an air cleaner. J Radioanal Nucl Chem 279:885–891CrossRefGoogle Scholar

Copyright information

© Akadémiai Kiadó, Budapest, Hungary 2011

Authors and Affiliations

  • Gye-Nam Kim
    • 1
  • Suk-Chol Lee
    • 1
  • Dong-Bin Shon
    • 1
  • Hye-Min Park
    • 1
  • Wang-Kyu Choi
    • 1
  • Jei-Kwon Moon
    • 1
  1. 1.Korea Atomic Energy Research InstituteDaejeonRepublic of Korea

Personalised recommendations