TITLE

The oxidative-dissolution behaviors of fission products in a Na2CO3–H2O2 solution

AUTHOR(S)
Lee, E. H.; Lim, J. K.; Chung, D. Y.; Yang, H. B.; Yoo, J. H.; Kim, K. W.
PUB. DATE
September 2009
SOURCE
Journal of Radioanalytical & Nuclear Chemistry;Sep2009, Vol. 281 Issue 3, p339
SOURCE TYPE
Academic Journal
DOC. TYPE
Article
ABSTRACT
This study was carried out to investigate the characteristics of an oxidative-dissolution of fission products (FP) when uranium (U) is dissolved in a Na2CO3–H2O2 carbonate solution. Simulated FP-oxides which contained 12 components were added to the solution to examine their dissolution behaviors. It was found that H2O2 was an effective oxidant to minimize the dissolution of FP. For the 0.5 M Na2CO3–0.5 M H2O2 solution, such elements as Re, Te, Cs, and MoO2 were dissolved with yields of 98 ± 2%, 98 ± 2%, 93 ± 2%, and 26 ± 3%, respectively, for 2 h. Among these components, Re, Te, and Cs were completely dissolved within 10–20 min without regard to the concentrations of Na2CO3, and H2O2 due to their high solubility in the carbonate solution with and without H2O2. However, MoO2 was very slowly dissolved and its yield was 29 ± 3% for 4 h. The pH of the dissolved solution revealed the greatest influence on the dissolution yields of the FP, exhibiting the most effective pH condition in the range of 10–12 in order to create a considerable suppression of the co-dissolution of FP during the oxidative-dissolution of U.
ACCESSION #
44513661

 

Related Articles

  • How do we define the concepts specific activity, radioactive concentration, carrier, carrier-free and no-carrier-added? de Goeij, J.J.M.; Bonardi, M.L. // Journal of Radioanalytical & Nuclear Chemistry;Jan2005, Vol. 263 Issue 1, p13 

    The fission of highly enriched uranium (HEU) by thermal neutrons creates dozens of isotopic products. The Isotope and Nuclear Chemistry Group participates in programs that involve analysis of“fresh' fission products by beta counting following radiochemical separations. This is a laborious...

  • Uranium detection in solid radwastes with a CdZnTe spectrometric detector. Potapov, V.; Stepanov, V.; Volkovich, A.; Smirnov, S. // Atomic Energy;Dec2012, Vol. 113 Issue 2, p130 

    A method of detecting uranium in solid radwastes on the basis of the characteristic radiation is described. As a rule, the characteristic radiation of uranium is excited by radiation contained in long-lived radionuclide wastes or internal fission products of irradiated fuel. In wastes stored for...

  • Spectrometric method of evaluating spent nuclear fuel characteristics. V. Potapov; A. Volkovich; Yu. Simirskii // Atomic Energy;May2009, Vol. 106 Issue 5, p348 

    A spectrometric method of identifying spent fuel assemblies according to the type of fuel elements present in them is described. The method is based on the results of spectrometric measurements and subsequent analysis of the radiation from fission products and the characteristic radiation from...

  • Instrumental neutron activation analysis in geochemistry: Emphasis on spectral and uranium fission product interferences. Tshiashala, M. D. A. // Journal of Radioanalytical & Nuclear Chemistry;Sep2005, Vol. 265 Issue 3, p511 

    The accuracy of the analytical results may suffer from unsolved interferences both spectral or due to U fission products despite progress performed in electronics and informatics in instrumental neutron activation analysis. This contribution deals with the correction of spectral and U fission...

  • HEU measurements of holdup and recovered residue in the deactivation and decommission activities of the 321-M Reactor Fuel Fabrication Facility at the Savannah River Site. Dewberry, R. A.; Salaymeh, S. R.; Casella, V. R.; Moore, F. S. // Journal of Radioanalytical & Nuclear Chemistry;Mar2006, Vol. 267 Issue 3, p515 

    This paper contains a summary of the holdup and material control and accountability (MC&A) assays conducted for the determination of highly enriched uranium (HEU) in the deactivation and decommissioning (D&D) of the Reactor Fuel Fabrication Facility at the Savannah River Site (SRS). The facility...

  • Impatient Iran.  // New Scientist;8/6/2005, Vol. 187 Issue 2511, p5 

    The article informs that Iran has announced last week that it was going to resume processing nuclear fuel at its Uranium Conversion Facility (UCF) in Isfahan, a plant it voluntarily mothballed 20 months ago. On August 1, the Iranian news agency IRNA quoted Gholam Ali Haddad Adel, Iran's...

  • Paladin Energy spills radioactive material at Malawi mine.  // African Business News;2/17/2014, p16 

    The article reports that radioactive material spill has occurred at uranium production company Paladin Energy Ltd.'s Kayelekera mine in Malawi. It states that the incident occurred when an uranium oxide container overturned and got punctured by a tree stump. The company mentions that it has...

  • Formal oxidation potentials of actinide couples in K10P2W17O61 solutions. Yusov, A.; Shilov, V.; Fedoseev, A. // Radiochemistry;Mar2007, Vol. 49 Issue 2, p152 

    The formal oxidation potentials of the M(VI)/M(V), M(V)/M(IV), and M(IV)/M(III) couples for actinides from U to No and of the M(IV)/M(III) couples for some actinides in 1 M H+ or 1 M Na+ (pH ∼5–5.5) solutions containing K10P2W17O61 were calculated from the data on stability of...

  • Investigation of the partitioning of fission products between the metallic and oxide phases of melt in a VVER-1000 vessel during a serious accident. V. Asmolov; V. Zagryazkin; D. Tsurikov; V. Uglov; V. Vishnevskii; E. D’yakov; A. Kotov; V. Repnikov // Atomic Energy;Jul2008, Vol. 105 Issue 1, p1 

    Abstract  The results of investigations of the interaction of U-Zr-B-C-O melt with steel, performed as part of the OECD MASCA program, are presented. It is established that the presence of Mo, Ru, Sr, Ba, Ce, and La in the melt does not qualitatively affect the interaction with structural...

Share

Read the Article

Courtesy of THE LIBRARY OF VIRGINIA

Sorry, but this item is not currently available from your library.

Try another library?
Sign out of this library

Other Topics