Abstract
A non-destructive wavelength dispersive X-ray fluorescence (WDXRF) spectrometric method for direct determination of uranium and plutonium in as fabricated annular sintered (U, Pu)O2 mixed oxide (MOX) pellets avoiding the traditional cumbersome sample preparation involving dissolution or comminution–pelletization of sample has been developed. Sintered (U, Pu)O2 MOX pellets were directly analyzed using this method by taking the sample pellets inside an indigenously developed special collet which was loaded in the spectrometer for WDXRF measurements. The developed methodology has the utility for regular analysis of samples in fuel fabrication facilities. The relative standard deviation of the analytical results for U and Pu using WDXRF were found to be better than ± 0.13% and ± 0.31% (n = 10) respectively and equivalent plutonium content obtained are in close agreement with the standard titrimetric methods.
Similar content being viewed by others
References
Sinha RK, Kakodkar A (2006) Design and development of the AHWR—the Indian thorium fuelled innovative nuclear reactor. Nucl Eng Des 236:683–700
Dey PK, Bansal NK (2006) Spent fuel reprocessing: a vital link in Indian nuclear power program. Nucl Eng Des 236:723–729
Chetal SC, Balasubramaniyan V, Chellapandi P, Mohanakrishnan P, Puthiyavinayagam P, Pillai CP, Raghupathy S, Shanmugham TK, Pillai Sivathanu C (2006) The design of the prototype fast breeder reactor. Nucl Eng Des 236:852–860
Panakkal JP, Mukherjee D, Kamath HS (2008) Nondestructive evaluation of uranium-plutonium mixed oxide (MOX) fuel elements by gamma autoradiography. In: 17th World conference on nondestructive testing, Shanghai, China
Mishra AK, Shelke BK, Yadav MK, Mohd A, Kumar A, Prasad GJ (2013) Developments in fabrication of annular MOX fuel pellet for Indian fast reactor. In: International conference on fast reactors and related fuel cycles: safe technologies and sustainable scenarios (FR13) Paris, France, pp 1–10
Khan KB (2008) Chemical quality control of FBTR fuel. IANCAS Bull 7:200–207
Davies W, Gray W (1964) A rapid and specifc titrimetric method for the precise determination of uranium using iron (II) sulphate as reductant. Talanta 11:1203–1211
Drummond JL, Grant RA (1966) Potentiometric determination of plutonium by argentic oxidation, ferrous reduction and dichromate titration. Talanta 13:477–488
Schults WD (1963) Application of controlled-potential coulometry to the determination of plutonium. A review. Talanta 10:883–849
Xavier M, Nair PR, Lohithakshan KV, Mahatre SG, Jain HC (1991) Determination of uranium in the presence of iron and plutonium by Ti(III) reduction and biamperometric titration. J Radioanal Nucl Chem 148(2):251–256
Bertin EA (1984) Principle and practice of X-ray spectrometric analysis, 2nd edn. Plenum, New York
Misra NL, Tiwari MK, Sanjay Kumar S, Dhara S, Singh AK, Lodha GS, Deb SK, Gupta PD, Aggarwal SK (2013) Synchrotron-induced EDXRF determination of uranium and thorium in mixed uranium–thorium oxide pellets. X-Ray Spectrom 42(1):4–7
Dhara S, Prabhat P, Misra NL (2015) Direct compositional characterization of (U,Th)O2 powders, microspheres, and pellets using TXRF. Anal Chem 87(20):10262–10267
Pella PA, Baeckmann AV (1969) X-ray spectrometric determination of uranium and plutonium in solutions of spent nuclear fuels. Anal Chim Acta 47:431–438
Diels P, Lecocq R (1982) Determination of the Pu/U + Pu ratio in FBR fuel pellets by X-ray fluorescence analysis. J Nucl Mater 106(1–3):115–120
Jayadevan NC, Chawla KL, Singh Mudher KD, Dahale ND, Chackraburtty DM (1984) X-ray spectrometric methods for the determination of plutonium and uranium in their mixed oxide samples. J Radioanal Nucl Chem 82:125–134
Pandey A, Dhara S, Khan FA, Kelkar A, Yadav R, Kumar P, Sathe DB, Bhatt RB, Behere PG (2020) Direct determination of uranium in sintered deeply depleted uranium oxide pellets by wavelength dispersive X-ray fluorescence spectrometry. J Radioanal Nucl Chem 323(1):275–281
Eberle AR, Lemer MW, Goldbeck CG, Rodden CJ (1970) U.S. Atomic Energy Commission, New Brunswick Laboratory report (NBL)-252
Orr RM, Sims HE, Taylor RJ (2015) A review of plutonium oxalate decomposition reactions and effects of decomposition temperature on the surface area of the plutonium dioxide product. J Nucl Mater 465:756–773
Jayaraj RN (2005) Processing of uranium from MDU to UO2 pellets. IANCAS Bull 4(3):184–190
Mishra S, Raul SN, Godbole ID, Mishra AK, Kumar A, Kamath HS (1999) Use of polyethylene glycol and oleic acid in fabrication of nuclear fuel pellets. In: Proceedings of PMAI, vol 26, pp 87–89
Vrinda Devi KV, Sathe DB, Soreng T (2017) Fissile worth of MOX fuel: a non destructive study. Nucl Eng Des 325:124–128
Takahashi G (2015) Sample preparation for X-ray fluorescence analysis. Rigaku J 31(1):26–30
Pandey A, Dhara S, Khan FA, Kelkar A, Kumar P, Bhatt RB, Behere PG (2019) Analysis of Th and U in thorium-based mixed-oxide fuel using wavelength dispersive X-ray fluorescence spectrometer. J Radioanal Nucl Chem 319:775–781
Pandey A, Khan FA, Kelkar A, Purohit P, Kumar P, Sathe DB, Bhatt RB, Behere PG (2020) Determination of trace amounts of uranium in plutonium oxide by wavelength dispersive X-ray fluorescence spectrometry. J Radioanal Nucl Chem. https://doi.org/10.1007/s10967-020-07116-6
Wick OJ (ed) (1980) Plutonium handbook—a guide to technology, vol 1. American Nuclear Society, United States
Morse LR, Edlestein NM, Fuger J, Katz JD (eds) (2006) The chemistry of actinide and transactinide elements, vol 1, 3rd edn. Springer, Berlin
Annual Book of ASTM Standards (2011) Standard guide for design criteria for plutonium glove boxes, Vol. 12.01 Nuclear Energy (I) C852-09, pp 226–230
Aher S, Pandey A, Khan FA, Das DK, Kumar S, Behere PG, Mohd. A (2015) Glove box adaptation, installation and commissioning of WD-XRF system for determination of PuO2 in MOX fuel samples. In: Proceedings of DAE-BRNS symposium on recent advances in nuclear fuel cycle activities, pp 56–58
Acknowledgements
The authors would like to acknowledge to the colleagues from Oxide Fuel Section, FF and Analytical Lab, FF for providing the samples and carrying out various analyses. We thank Dr. G. Singh, FF for his valuable suggestions and support. They also show their sincere thanks to Dr. N. L. Mishra, Ex. Head, X-ray Spectroscopy Section, Fuel Chemistry Division, BARC, Mumbai, India for his keen interest, extended co-operation and enormous support during the course of this work.
Author information
Authors and Affiliations
Corresponding author
Rights and permissions
About this article
Cite this article
Pandey, A., Khan, F.A., Kelkar, A. et al. Non-destructive determination of uranium and plutonium in annular (U, Pu)O2 mixed oxide sintered pellets by wavelength dispersive X-ray fluorescence spectrometry. J Radioanal Nucl Chem 326, 423–433 (2020). https://doi.org/10.1007/s10967-020-07309-z
Received:
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10967-020-07309-z