TITLE

Plutonium process monitoring (PPM) system

AUTHOR(S)
Wong, A. S.; Ricketts, T. E.; Pansoy-Hejlvik, M. E.; Ramsey, K. B.; Hansel, K. M.; Romero, M. K.
PUB. DATE
July 2000
SOURCE
AIP Conference Proceedings;2000, Vol. 532 Issue 1, p331
SOURCE TYPE
Academic Journal
DOC. TYPE
Article
ABSTRACT
In mid-1980, Marsh and Pope developed an online gamma system to monitor americium, uranium and plutonium gamma rays during anion-exchange process for plutonium aqueous recovery operations. It has been shown that the real-time elution profiles of actinide impurities are important for plutonium loss via break-through, waste minimization, and process monitoring. However, the current monitoring equipment and data acquisition software are obsolete and are frequently problematic. In 1999, we redesigned the on-line gamma monitoring system in collaboration with Perkin-Elmer ORTEC (Oak Ridge, TN) to enhance and upgrade the current system. This paper describes the new integrated plutonium process monitoring (PPM) system for the aqueous plutonium recovery and anion-exchange processes at the Los Alamos Plutonium Facility. © 2000 American Institute of Physics.
ACCESSION #
5663336

 

Related Articles

  • Evaluation of N,N-dihexyloctanamide as an alternative extractant for spent fuel reprocessing: batch and mixer settler studies. Pathak, P.N.; Prabhu, D.R.; Kumari, Neelam; Kanekar, A.S.; Manchanda, V.K. // Desalination & Water Treatment;Jan2012, Vol. 37/38 Issue 1-3, p40 

    Solvent extraction studies carried out at BARC, India on the evaluation of N,N-dialkyl amides as alternative extractants to tri-n-butyl phosphate (TBP) for reprocessing of spent fuel have suggested that straight chain N,N-dihexyloctanamide (DHOA) is promising alternative to TBP for the...

  • Studies on purification of plutonium from silver ions. Joshi, A. R.; Patil, Abhay V.; Kasar, U. M. // Journal of Radioanalytical & Nuclear Chemistry;Oct2010, Vol. 286 Issue 1, p67 

    Precipitation and solvent extraction methods have been investigated for the purification of plutonium from silver from the solution generated during oxidative dissolution of plutonium oxide using Ag(II) ions. Initial experiments have been carried out using thorium as representative of plutonium....

  • Plutonium hydrolysis and the double double-point. Silver, G. // Journal of Radioanalytical & Nuclear Chemistry;Feb2011, Vol. 287 Issue 2, p591 

    There is uncertainty about the numerical value of the first hydrolysis constant of the tetravalent plutonium ion. A new method for discriminating between the claims is illustrated. It suggests the traditional estimates of that constant are closer to its true value than a singular result based on...

  • Complexation of plutonium(IV) with sulfate at variable temperatures. Xia, Y. X.; Friese, J. I.; Moore, D. A.; Bachelor, P. P.; Rao, L. // Journal of Radioanalytical & Nuclear Chemistry;Oct2007, Vol. 274 Issue 1, p1 

    The complexation of plutonium(IV) with sulfate at variable temperatures has been investigated by solvent extraction method. A NaBrO3 solution was used as holding oxidant to maintain the plutonium(IV) oxidation state throughout the experiments. The distribution ratio of Pu(IV) between the organic...

  • 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,...

  • Extraction and separation of uranium, plutonium and americium from MOX fuel rejected waste and analytical phosphoric acid based waste using organophosphorus extractants. Karande, A. P.; Mallik, G. K.; Panakkal, J. P.; Kamath, H. S.; Bhargava, V. K.; Mathur, J. N. // Journal of Radioanalytical & Nuclear Chemistry;May2003, Vol. 256 Issue 2, p185 

    Examines the extraction of uranium, plutonium and americium from mixed oxide fuel waste and analytical phosphoric acid based-waste. Use of organophosphorus compounds as extractants; Dissolution of the mixed oxide fuel waste in nitric oxide; Solvent extraction technique.

  • Modeling of Pu(VI) distribution coefficients in 30 % TBP based PUREX process. Kumar, Shekhar; Kamachi Mudali, U. // Journal of Radioanalytical & Nuclear Chemistry;Mar2013, Vol. 295 Issue 3, p1951 

    Hexavalent plutonium (Pu(VI)) is an important solute in the PUREX (plutonium uranium extraction) process. In 30 % TBP based PUREX solvent extraction system, distribution coefficient of Pu(VI) is much lower than that of Pu(IV). This lower distribution coefficient of Pu(VI) may cause unexpected Pu...

  • Development of solvent extraction scheme for reprocessing of advanced heavy water reactor spent fuel using N,N-Dihexyl octanamide as extractant. Kumari, Neelam; Pathak, P.N.; Prabhu, D.R.; Manchanda, V.K. // Desalination & Water Treatment;Jan2012, Vol. 37/38 Issue 1-3, p159 

    Distribution studies on Th(IV), Pa(V), U(VI) and Pu(IV) were carried out employing tri-nbutyl phosphate (TBP) and N,N-dihexyl octanamide (DHOA) as extractants under proposed advanced heavy water reactor (AHWR) spent fuel feed conditions. DHOA was found promising for selective extraction of U/Pu...

  • Partitioning of plutonium and uranium in aqueous medium using hydroxyurea as reducing agent. Sivakumar, P.; Meenakshi, S.; Rao, R. // Journal of Radioanalytical & Nuclear Chemistry;May2012, Vol. 292 Issue 2, p603 

    A new process for the partitioning of plutonium and uranium during the reprocessing of spent fuel discharged from fast reactor was optimised using hydroxyurea (HU) as a reductant. Stoichiometric ratio of HU required for the reduction of Pu(IV) was studied. The effect of concentration of uranium,...

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