Abstract
In the present study, the dissolution kinetics of simulated urania, ceria MOX fuel pellets in nitric acid under PUREX process condition has been investigated. Influence of various parameters like initial concentration of nitric acid, temperature and Ce composition on rate of dissolution of MOX fuel pellet was studied. Rate expression was developed by considering Langmuir–Hinshelwood mechanism to describe the dissolution of MOX fuel pellet in nitric acid. The estimated value of activation energy of about 40–50 kJ mol−1 confirms the intrinsic nature of dissolution kinetics.
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Abbreviations
- HNO3 :
-
Nitric acid
- UO2 :
-
Uranium dioxide
- CeO2 :
-
Cerium oxide
- MOX:
-
Mixed oxide
- U:
-
Uranium
- Pu:
-
Plutonium
- Ce:
-
Cerium
- v B :
-
Stoichiometric coefficient of UO2
- v AB :
-
Stoichiometric coefficient of HNO3 for UO2 dissolution
- v E :
-
Stoichiometric coefficient of CeO2
- v AE :
-
Stoichiometric coefficient of HNO3 for CeO2 dissolution
- C:
-
Cocentration, kmol m−3
- kLA :
-
Mass transfer coefficient between the reaction surface and the bulk liquid phase, m/s
- nA :
-
Number of mols of nitric acid in reaction mixture
- nBL :
-
Number of mols of uranium in reaction mixture
- nEL :
-
Number of mols of cerium in reaction mixture
- kB :
-
Rate constant for UO2 dissolution, kmol m−5 s−1
- kE :
-
Rate constant for CeO2 dissolution, kmol m−5 s−1
- rsB :
-
Rate of surface reaction for UO2 dissolution, kmol m−5 s−1
- rsE :
-
Rate of surface reaction for CeO2 dissolution, kmol m−5 s−1
- AtB :
-
Reactive surface area for UO2 dissolution at any time, m2
- AtE :
-
Reactive surface area for CeO2 dissolution at any time, m2
- θ AU :
-
The surface coverage of HNO3 on solid phase by adsorption for UO2 dissolution (fractional coverage)
- θ AE :
-
The surface coverage of HNO3 on solid phase by adsorption for CeO2 dissolution (fractional coverage)
- T:
-
Temperature, K
- θ A :
-
Surface coverage of HNO3 on solid phase by adsorption
- Kad :
-
Adsorption constant, m3 kmol−1
- a:
-
Shape factor
- Ap :
-
Reactive surface area of particle, m2
- Vp :
-
Volume of particle, m3
- R:
-
Radius of particle, m
- n:
-
Amount of unreacted solid at any time, t
- n0 :
-
Amount of solid material at time, t = 0
- M:
-
Molecular wt of MOX pellet, gmmol−1
- mP :
-
Mass of solid particle, kg
- x0B :
-
Mole fraction of UO2
- n0B :
-
Amount of UO2 in solid partcile at time, t = 0
- nB :
-
Unreacted amount of UO2 in solid particle at any time, t
- x0E :
-
Mole fraction of CeO2
- n0E :
-
Amount of CeO2 in solid particle at time, t = 0
- nE :
-
Unreacted amount of CeO2 in solid particle at any time, t
- VL :
-
Volume of the reaction mixture, m3
- L:
-
Liquid phase/Reaction mixture
- B:
-
UO2/Uranium
- A:
-
Nitric acid
- E:
-
CeO2/Cerium
- S:
-
Concentration at solid surface
- b:
-
Bulk liquid phase
- t:
-
Time
- 0/t = 0:
-
Initial condition, at t = 0
- f:
-
Final condition
- p:
-
Solid particle
- Calc:
-
Calculated
- Exp:
-
Experimental
- ρp :
-
Density of solid particle, kg m−3
- σ:
-
Specific surface area of solid particle, m2 kg−1
References
Murray RL, Holber KE (2015) Nuclear energy: an introduction to the concepts, systems and applications of nuclear processes, 7th edn. Elsevier
Department of Atomic Energy Annual Report., 2019–2020 https://dae.gov.in/writereaddata/Annual2019-2020e.pdf
Judd AM (1981) Fast breeder reactors: an engineering introduction. Pergamon Press, Oxford
Ryan JL. Bray LA (1980) Dissolution of plutonium dioxide—a critical review. In: Navratil JD, Schultz WW (eds) Actinide separations, p. 499. ACS Symposium Series, 17th ACS National Meeting, Honolulu, HI
Desigan N, Ganesh S, Pandey NK (2021) Dissolution behavior of Fast Reactor MOX nuclear fuel pellets in nitric acid medium. J Nucl Mat. https://doi.org/10.1016/j.jnucmat.2021.153077
Kim HS, Joung CY, Lee BH, Oh JY, Koo YH, Heimgartner P (2008) Applicability of CeO2 as a surrogate for PuO2 in a MOX fuel development. J Nucl Mat 378:98–104
Marra JC, Cozzi AD, Pierce RA, Pareizs JM, Jurgensen AR, Missimer DM (2001) Cerium as a Surrogate in the Plutonium Immobilized Form. WSRC-MS-2001–00007; Westinghouse Savannah River Company, Aiken, SC 29808. https://sti.srs.gov/fulltext/ms2001007/ms2001007.html
Levenspiel O (1999) Chemical reaction engineering, 3rd edn. Wiley, New York
Salmi T, Grenman H, Warna J, Murzin DYu (2013) New modeling approach to liquid–solid reaction kinetics: from ideal particle to real particle. Chem Eng Res Des 91:1876
BlainHT (1960) Rep. Congr. Atom. Energy Commn. U.S. HW-66320
Fukasawa T, Ozawa Y (1986) Relationship between dissolution rate of uranium dioxide pellets in nitric acid solutions and their porosity. J Radioanal Nucl Chem Lett 106(6):345
Fukasawa T, Ozawa Y, Kawamura F (1991) Generation and decomposition behaviour of nitrous acid during dissolution of UO2 pellets by nitric acid. Nucl Technol 94:108
Hodgson TD (1987) Proceedings of international conference on nuclear fuel reprocessing and waste management. RECOD 87, France, 591
Homma S, Koga J, Matsumoto S (1993) Dissolution rate equation of UO2 pellet. J Nucl Sci Technol 30:959
Ikeda Y, Yasuike Y, Nishimura K, Hasegawa S, Takashima Y (1995) Kinetic study on dissolution of UO2 powders in nitric acid. J Nucl Mater 224:266
Ikeda Y, Yasuike Y, Takashima Y, Park YY, Asano Y, Tomiyasu H (1993) 17O NMR study on dissolution reaction of UO2 in nitric acid mechanism of electron transfer. J Nucl Sci Technol 30(9):962
Inoue A, Sujino T (1984) Dissolution rates of U3O8 Powders in nitric acid. Ind Eng Chem Process Des Dev 23:122
Inoue A (1986) Mechanism of the oxidative dissolution of UO2 in HNO3 solution. J Nucl Mater 138:152
Mineo H, Isogai H, Morita Y, Uchiyama G (2004) An investigation into dissolution rate of spent nuclear fuel in aqueous reprocessing. J Nucl Sci Technol 41(2):126
Shabbir M, Robins RG (1968) Kinetics of the dissolution of uranium dioxide in nitric acid I. J Appl Chem 18:129
Taylor RF, Sharratt EW, Chazal LE, Logsdail DH (1963) Dissolution rate of uranium dioxide sintered pellets in nitric acid systems. J Appl Chem 13:32
Desigan N, Elizabeth A, Remya M, Pandey NK, Kamachi Mudali U, Natarajan R, Joshi JB (2015) Dissolution kinetics of Indian PHWR natural UO2 fuel pellets in nitric acid: effect of initial acidity and temperature. Prog Nucl Energy 83:52
Elizabeth A, Desigan N, Pandey NK, Joshi JB (2020) Analysis of kinetic data for the dissolution of UO2 fuel pellets in nitric acid. J Rad Anal Nucl Chem 324:211–218
Barney GS (1977) The kinetics of plutonium oxide dissolution in nitric/hydrofluoric acid mixtures. J Inorg Nucl Chem 39:1665
Harmon HD (1975) Evaluation of fluoride, cerium (IV), and cerium (IV)-fluoride mixtures as dissolution promoters for PuO2 scarp recovery processes. Report DP-1383
Horner D, Crouse DJ, Mailen JC (19770) Cerium-promoted dissolution of PuO2 and PuO2– UO2 in nitric acid. ORNL/TM-4716
Kazanjian AR, Stevens JR (1984) Dissolution of plutonium oxide in nitric acid at high hydrofluoric acid concentrations. Report RFP-3609
Ryan JL, Bray L, Wheelwright EJ, Bryan GH (1990) Catalyzed electrolytic plutonium oxide dissolution (CEPOD): the past seventeen years and future potential. PNL-SA-18018, CONF-900846–5, 39
Uriarte AL, Rainey RH (1965) Dissolution of high-density UO2, PuO2, and UO2-PuO2 pellets in inorganic acids. Oak Ridge National laboratory report ORNL-3695
Zawodzinski C, Smith WH, Martinez KR (1993) Kinetic studies of the electrochemical generation of Ag(ll) ion and the catalytic oxidization of selected organics. In: Proceedings of the symposium on environmental aspects of electrochemistry and photoelectrochemistry, Honolulu, HI (United States)
Bourges J, Madic C, Koehly G, Leconte M (1986) Dissolution of plutonium bioxide in nitric medium with electrogenerated silver (II). J Less Comm Met 122:303–311
Cooley CR (1971) Status of electrolytic dissolution for LMFBR fuels. Report number HEDLTME--71–123. https://doi.org/10.2172/4732897.
Ryan JL, Bray LA, Boldt AL (1987) Dissolution of PuO2 or NpO2 using electrolytically regenerated reagents. US Patent 4686019
Desigan N, Bhatt N, Shetty MA, Sreekumar GKP, Pandey NK, Mudali UK, Natarajan R, Joshi JB (2019) Dissolution of nuclear materials in aqueous acid solutions. Rev Chem Eng 35(6):707–734. https://doi.org/10.1515/revce-2017-0063
Kolman DG, Park YS, Tan M, Hanrahan RJ Jr, Butt DP (1999) An assessment of the validity of cerium oxide as a surrogate for plutonium oxide gallium removal studies. LANL Report LA-UR-99-0491
Lee YW, Kim HS, Kim SH, Joung CY, Na SH, Ledergerber G, Heimgartner P, Pouchon M, Burghartz M (1999) Preparation of simulated inert matrix fuel with different powders by dry milling method. J Nucl Mater 274:7
Markin TL, Street RS, Crouch EC (1970) Thermodynamic data for U–Ce-oxides. J Inorg Nucl Chem 32:59. Lorenzelli R, Touzelin B (1980). J Nucl Mater 95:290.
Desigan N, Maji D, Ananthasivan K, Pandey NK, Kamachi Mudali U, Joshi JB (2019) Dissolution behavior of simulated MOX nuclear fuel pellets in nitric acid. Prog Nucl Energy 116:1–9
Carberry JJ (1976) Chemical and catalytic reaction engineering. Mc Graw-Hill, New York
Maji D, Ananthasivan K, Venkata Krishnan R, Balakrishnan S, Joseph K, Das Gupta A (2018) Nanocrystalline (U0.5 Ce0.5)O2±x solid solutions through citrate gel-combustion. J Nucl Mat 502:370–379
Doraiswamy LK, Sharma MM (1984) Heterogeneous reactions: analysis, examples, and reactor design. Wiley, New York
Rigby SP, Fletcher RS, Riley SN (2004) Characterization of porous solids using integrated nitrogen sorption and mercury porosimetry. Chem Eng Sci 59(1):41–51. https://doi.org/10.1016/j.ces.2003.09.017
Grenman H, Salmi T, Murzin DY (2011) Solid liquid reaction kinetics-experimental aspects and model development. Rev Chem Eng 27 (2011):53–77
Salmi T, Grenman H, Warna J, Murzin DYu (2011) Revisiting shrinking particle and product layer models for fluid–solid reactions: from ideal surfaces to real surfaces. Chem Eng Process 50:1076
Desigan N, Bhatt NP, Pandey NK, Kamachi Mudali U, Natarajan R, Joshi JB (2017) Mechanism of dissolution of nuclear fuel in nitric acid relevant to nuclear fuel reprocessing. J Radioanal Nucl Chem 312(1):141
Davidson JK, Haas WO Jr, Meroherter JL, Miller RS, Smith DJ (1959) The fast oxide breeder: the fuel cycle. KAPL-1757
Ferris LM, Kibbey AH (1960) Sulfex-thorex and darex-thorex processes for the dissolution of consolidated edison power reactor fuel: laboratory development. ORNL-2934
Flagg JF (1960) Chemical processing of reactor fuels. Academic Press, New York, p 90
Desigan N, Pandey NK, Joshi JB (2021) Influence of the concentration of nitric acid on the composition of NOX gas evolved during the dissolution of nuclear fuel and its implications on the PUREX process. Prog Nucl Energy 135:103704. https://doi.org/10.1016/j.pnucene.2021.103704
Grenman H, Ingves M, Warna J, Corander J, Murzin DYu, Salmi T (2011) Common potholes in modelling solid-liquid reactions-methods for avoiding them. Chem Eng Sci 66:4459
Desigan N (2017a) Chemical aspects of the dissolution of fast reactor nuclear fuel. Ph.D. Thesis, HBNI, Mumbai. https://sg.inflibnet.ac.in/handle/10603/274476
Butcher JC (2016) Numerical methods for ordinary differential equations, 3rd edn. Wiley, New York
Ikeuchi H, Shibata A, Sano Y, Koizumi T (2012) Dissolution behaviour of irradiated mixed oxide fuels with different plutonium contents. Proc Chem 7:77–83
Kizim NF (1992) The dynamic separation of substances by liquid–liquid extraction. Russ Chem Rev 61:830–850
Yu JF, Ji C (1992) Interfacial chemistry and kinetics-controlled reaction mechanism of organophosphoric acid mixed extraction systems. Chem J Chin Univ 13:224–226
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Augustine, E., Desigan, N., Rajeev, R. et al. Kinetics of dissolution of simulated (U–Ce) MOX fuel pellet in nitric acid. J Radioanal Nucl Chem 331, 4529–4539 (2022). https://doi.org/10.1007/s10967-022-08582-w
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DOI: https://doi.org/10.1007/s10967-022-08582-w