TITLE

Calculation of structural and thermodynamic properties of Pu-doped thorium phosphate diphosphate Th[sub 4-x]Pu[sub x](PO[sub 4])[sub 4]P[sub 2]O[sub 7]

AUTHOR(S)
Meis, C.
PUB. DATE
July 2000
SOURCE
AIP Conference Proceedings;2000, Vol. 532 Issue 1, p360
SOURCE TYPE
Academic Journal
DOC. TYPE
Article
ABSTRACT
The synthesis and characterization of the thorium phosphate diphosphate, Th[sub 4](PO[sub 4])[sub 4]P[sub 2]O[sub 7](TPD), has been published previously.(1,2) It has been proposed as a host phase for plutonium and actinides disposal.(3,4) However, we don’t know a lot about its mechanical and thermodynamic properties as well as about their variation with respect to plutonium concentration. Furthermore, its behavior under irradiation is unknown while the threshold displacement energies relative to the a-recoil have never been estimated. Consequently, a theoretical study on these significant questions is actually being carried out, and we present here the first results obtained. © 2000 American Institute of Physics.
ACCESSION #
5663322

 

Related Articles

  • Alpha spectroscopic analysis of actinides (Th, U and Pu) after separation from aqueous solutions by cation-exchange and liquid extraction. Kiliari, Tasoula; Pashalidis, Ioannis // Journal of Radioanalytical & Nuclear Chemistry;Jun2010, Vol. 284 Issue 3, p547 

    The radioactivity concentration of 236Pu, 232U and 228Th in aqueous samples has been determined by means of alpha spectroscopy after chemical separation and pre-concentration of the radionuclides by cation exchange and liquid–liquid extraction using the Chelex-100 resin and 30%...

  • XANES and EXAFS studies of plutonium(III, VI) sorbed on thorium oxide. Drot, R.; Ordonez-Regil, E.; Simoni, E.; Auwer, Ch. Den; Moisy, Ph. // AIP Conference Proceedings;2000, Vol. 532 Issue 1, p93 

    This work deals with the influence of the oxidation state of plutonium on the structure of the sorbed complex. X-ray absorption spectroscopy has been chosen to perform this study. We have considered thorium oxide as a retention matrix because, on one hand, it is a sparingly soluble material;...

  • Effect of the Structure of o-Methyleneoxyphenyldiphosphine Dioxides on Their Extractive Power and Selectivity in Nitric Acid Solutions. Turanov, A. N.; Karandashev, V. K.; Fedoseev, A. M.; Rodygina, N. I.; Baulin, V. E. // Radiochemistry;Mar2005, Vol. 47 Issue 2, p177 

    Extraction of trace amounts of Pu(IV), U(VI), Th(IV), Am(III), and REEs(III) from nitric acid solutions with o-methyleneoxyphenyldiphosphine dioxides with phenyl ( I) and butyl ( II) substituents at the phosphoryl group is studied. The stoichiometry of extractable complexes in dichloroethane is...

  • Radio-toxicity of spent fuel of the advanced heavy water reactor. Anand, S.; Singh, K. D. S.; Sharma, V. K. // Radiation Protection Dosimetry;Jan2010, Vol. 138 Issue 1, p52 

    The Advanced Heavy Water Reactor (AHWR) is a new power reactor concept being developed at Bhabha Atomic Research Centre, Mumbai. The reactor retains many desirable features of the existing Pressurised Heavy Water Reactor (PHWR), while incorporating new, advanced safety features. The reactor aims...

  • Preparation, characterization and application of thorium oxalate for sorption of plutonium and americium from aqueous solution. Jayachandran, Kavitha; Bhanushali, R. D.; Pius, I. C.; Mukerjee, S. K. // Journal of Radioanalytical & Nuclear Chemistry;Oct2008, Vol. 278 Issue 1, p103 

    Synthetic inorganic exchangers exhibit good thermal and radiation stability. Thorium oxalate precipitate shows potential for co-precipitation of plutonium and americium from oxalate supernatant generated during plutonium oxalate precipitation. In the present study, efforts were made to prepare...

  • Validation of the fl ow-sheet proposed for reprocessing of AHWR spent fuel: counter-current studies using TBP. Dhami, Prem Singh; Jagasia, Poonam; Panja, Surajit; Naik, Prashant Waman; Achuthan, Padinhare Variam; Tripathi, Subhash Chandra; Munshi, Satish Kumar; Dey, Pran Krishna // Desalination & Water Treatment;Jan2012, Vol. 37/38 Issue 1-3, p184 

    A solvent extraction based flow-sheet, for reprocessing of spent fuel arising from Advanced Heavy Water Reactor (AHWR) for separation of uranium, plutonium and thorium using 5% TBP in n-dodecane, has been tested using laboratory scale mixer-settlers. Simulated feed solution containing thorium,...

  • The role of plutonium in nuclear power.  // Bulletin of the Atomic Scientists;Dec1976, Vol. 32 Issue 10, p12 

    The article discusses the function of plutonium in nuclear power development. Plutonium were produced from neutron bombardment of uranium-238 in plutonium breeder reactors. The plutonium produced from the breeder reactors releases a hundred times of as much energy produced from a pound of...

  • Plutonium and minor actinides utilization in Thorium molten salt reactor. Waris, Abdul; Aji, Indarta K.; Novitrian; Kurniadi, Rizal; Su'ud, Zaki // AIP Conference Proceedings;6/6/2012, Vol. 1448 Issue 1, p115 

    FUJI-12 reactor is one of MSR systems that proposed by Japan. The original FUJI-12 design considers Th/233U or Th/Pu as main fuel. In accordance with the currently suggestion to stay away from the separation of Pu and minor actinides (MA), in this study we evaluated the utilization of Pu and MA...

  • Supercritical-pressure water cooled thermal reactor with uranium—plutonium—thorium fuel cycle and bidirectional coolant flow articles. A. Glebov; A. Klushin // Atomic Energy;May2009, Vol. 106 Issue 5, p305 

    Computational results obtained for fuel assemblies and a core with uni- and bidirectional coolant flow are presented for a water-cooled reactor with a thermal neutron spectrum. It is shown that a bidirectional scheme for cooling fuel assemblies has advantages over a unidirectional scheme and...

Share

Read the Article

Courtesy of VIRGINIA BEACH PUBLIC LIBRARY AND SYSTEM

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

Try another library?
Sign out of this library

Other Topics