Journal of Radioanalytical and Nuclear Chemistry

, Volume 314, Issue 2, pp 1361–1365 | Cite as

Development of determination method of 93Mo content in metal waste generated at the Japan Power Demonstration Reactor

Article

Abstract

A separation method of Mo from Nb, Zr, and the matrix elements of rubble waste was modified to determine the content of 93Mo in metal waste. A separation scheme to treat 1 g of metal waste was established by optimizing the amount of ascorbic acid, the rinsing solution, and repeating of the procedure. A thin-layer source was prepared using direct drop deposition and evaporation to measure 93Mo content. Finally, 93Mo content in the metal waste generated at the Japan Power Demonstration Reactor was analyzed using the developed method.

Keywords

93Mo TEVA resin Low-level radioactive waste Metal waste Japan Power Demonstration Reactor 

References

  1. 1.
    International Atomic Energy Agency, IAEA (2009) Nuclear energy series No. NW-T-1.18, Determination and use of scalling factors for waste characterization in nuclear power plants, Wagramer strasse 5, P.O.Box 100, 1400 Vienna, AustriaGoogle Scholar
  2. 2.
    Hoshi A, Tsuji T, Tanaka K, Yasuda M, Watanabe K, Sakai A, Kameo Y, Kogure H, Higuchi H, Takahashi K (2011) Analysis of the radioactivity concentration in low-level radioactive waste generated from JPDR facilities, JAEA-Data/Code 2011-011Google Scholar
  3. 3.
    Tanaka K, Yasuda M, Watanabe K, Hoshi A, Tsuji T, Higuchi H (2013) Analysis of the radioactivity concentration in low-level radioactive waste generated from JPDR facilities part 2, JAEA-Data/Code 2013-008Google Scholar
  4. 4.
    Yasuda M, Tanaka K, Watanabe K, Hoshi A, Tsuji T, Kameo Y (2014) Analysis of the radioactivity concentration in low-level radioactive waste generated from JPDR facilities part 3, JAEA-Data/Code 2014-011Google Scholar
  5. 5.
    Ohmori H, Nebashi K, Shimada A, Tanaka K, Yasuda M, Hoshi A, Tsuji T, Ishimori K, Kameo Y (2015) Analysis of the radioactivity concentration in low-level radioactive waste generated from JPDR facilities part 4, JAEA-Data/Code 2015-029Google Scholar
  6. 6.
    Tsuji T, Kameo Y, Sakai A, Hoshi A, Takahashi K (2012) Study on the evaluation method to determine the radioactivity concentration in low-level radioactive wastes generated at JPDR facilities part 1, JAEA-Technology 2012-045Google Scholar
  7. 7.
  8. 8.
  9. 9.
    Shimada A, Ozawa M, Yabuki K, Kimiyama K, Sato K, Kameo Y (2014) Development of a separation method for molybdenum from zirconium, niobium, and major elements of rubble samples. J Chromatogr A 1371:163–167CrossRefGoogle Scholar
  10. 10.
    Shinohara N, Kohno N (1989) Rapid preparation of high-resolution sources for alpha-ray spectrometry of actinides in spent fuel. Appl Radiat Isot 40(1):41–45CrossRefGoogle Scholar
  11. 11.
    International Atomic Energy Agency (2005) Safety Reports Series, Derivation of Activity Concentration Values for Exclusion, Exemption and Clearance, ViennaGoogle Scholar

Copyright information

© Akadémiai Kiadó, Budapest, Hungary 2017

Authors and Affiliations

  1. 1.Department of Decommissioning and Waste ManagementJapan Atomic Energy AgencyNaka-gunJapan

Personalised recommendations