Evaluation of different integrated burnable absorber materials in fuel assemblies of Bushehr WWER-1000 nuclear reactor
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Zahra Papi
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Reza Pour-Imani
Abstract
Nowadays, reducing fuel consumption, fuel cost, and fuel waste is obtained by increasing the burnup and reactor cycle length as essential goals in nuclear power plants. Due to the scarcity of Iran’s uranium resources and the plan for using new types of fuel in the Water–Water Energetic Reactors (WWER-1000) at Bushehr Nuclear Power Plant (BNPP), utilizing Integral Burnable Absorbers (IBAs) is of great importance. In the present study, a neutronic evaluation has been conducted to investigate the variations of infinite multiplication factor versus burnup, reactivity swing, and power distribution in various IBAs, including Gd2O3-UO2, Er2O3-UO2, and Dy2O3-UO2. The results were compared with the standard burnable absorber in the BNPP reactor core (CrB2Al). It can be concluded that gadolinium IBA, with a concentration of 5%, has the greatest effect on the initial reactivity and reduces the reactivity swing by 19% compared to the CrB2Al BA. In addition, by using coaxial gadolinium-erbium IBA pins, as well as optimizing the neutronic condition, the reactor cycle length increased by 1.01 GWd/MTU compared to the standard Bushehr BA.
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: None declared.
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Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
References
Abu, S.M., Demin, V.M., and Savander, V.I. (2019). The effect of burnable absorbers (Gd and Eu) on the neutron physical characteristics of fuel assemblies of VVER-1000 reactors. J. Phys. Conf. 1189: 012003, https://doi.org/10.1088/1742-6596/1189/1/012003.Suche in Google Scholar
Chadwick, M.B., Herman, M., Obložinský, P., Dunn, M.E., Danon, Y., Kahler, A.C., Smith, D.L., Pritychenko, B., Arbanas, G., Arcilla, R., et al.. (2011). ENDF/B-VII. 1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data. Nucl. Data Sheets 112: 2887–2996, https://doi.org/10.1016/j.nds.2011.11.002.Suche in Google Scholar
Duderstadt, J.J. and Hamilton, L.J. (1976). Nuclear reactor analysis. Wiley, New York.Suche in Google Scholar
Frybortova, L. (2019). Recommended strategy and limitations of burnable absorbers used in VVER fuel assemblies. Nucl. Sci. Tech. 30: 1–14, https://doi.org/10.13182/NT99-A2956.Suche in Google Scholar
Galahom, A.A. (2017). Study of the possibility of using Europium and Pyrex alloy as burnable absorber in PWR. Ann. Nucl. Energy 110: 1127–1133, https://doi.org/10.1016/j.anucene.2017.08.052.Suche in Google Scholar
Galahom, A.A. (2016). Investigation of different burnable absorbers effects on the neutronic characteristics of PWR assembly. Ann. Nucl. Energy 94: 22–31, https://doi.org/10.1016/j.anucene.2016.02.025.Suche in Google Scholar
Gallmeier, F.X., Ferguson, P.D., Lu, W., Iverson, E.B., Muhrer, G., Holloway, S.T., Kelsey, C., Pitcher, E., Wohlmuther, M., and Micklich, B.J. (2010). The CINDER’90 transmutation code package for use in accelerator applications in combination with MCNPX. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States), Spallation Neutron Source (SNS).Suche in Google Scholar
Hadad, K. and Faghihi, F. (2014). Simulation of Bushehr reactor steady state by PARCS code and PMAXS library. J. Radiat. Nucl. Technol. 1: 9–15.Suche in Google Scholar
Khoshahval, F., Foroutan, S.S., Zolfaghari, A., and Minuchehr, H. (2016). Evaluation of burnable absorber rods effect on neutronic performance in fuel assembly of WWER-1000 reactor. Ann. Nucl. Energy 87: 648–658, https://doi.org/10.1016/j.anucene.2015.10.012.Suche in Google Scholar
Nguyen, X.H., Kim, C., and Kim, Y. (2019). An advanced core design for a soluble-boron-free small modular reactor ATOM with centrally-shielded burnable absorber. Nucl. Eng. Technol. 51: 369–376, https://doi.org/10.1016/j.net.2018.10.016.Suche in Google Scholar
Nguyen, X.H., Jang, S., and Kim, Y. (2020). Impacts of an ATF cladding on neutronic performances of the soluble‐boron‐free ATOM core. Int. J. Energy Res. 44: 8193–8207, https://doi.org/10.1002/er.5322.Suche in Google Scholar
NPP The Bushehr Unit 1 (2005). Final safety analysis report (FSAR), revision 0. AEOI, Moscow.Suche in Google Scholar
Pelowitz, D.B. (2008). MCNPX user’s manual report LA-CP-07-1473. Los Alamos National Laboratory.Suche in Google Scholar
Sanders, C.E. and Wagner, J.C. (2002). Study of the effect of integral burnable absorbers for PWR burnup credit. ORNL/TM-2000/321, in preparation.Suche in Google Scholar
Stoller Nuclear Fuel, NAC International (2001). The Implications of using enriched uranium Fuel with > 5 % 235U.Suche in Google Scholar
Uguru, E.H., Sani, S.A., Khandaker, M.U., and Rabir, M.H. (2020a). Investigation on the effect of 238U replacement with 232Th in small modular reactor (SMR) fuel matrix. Prog. Nucl. Energy 118: 103108, https://doi.org/10.1016/j.pnucene.2019.103108.Suche in Google Scholar
Uguru, E.H., Sani, S.A., Khandaker, M.U., and Rabir, M.H. (2020b). Actinide and non-actinide production from UO2 fuel in W-SMR: effects of gadolinium burnable absorber. Ann. Nucl. Energy 137: 107083, https://doi.org/10.1016/j.anucene.2019.107083.Suche in Google Scholar
© 2022 Walter de Gruyter GmbH, Berlin/Boston
Artikel in diesem Heft
- Frontmatter
- Application of the COCOSYS code in the safety evaluation of Czech nuclear power plants
- Improving of electric network feeding nuclear facility based on multiple types DGs placement
- Design and evaluation of ecological interface for Feedwater Deaerating Tank and Gas Stripper System based on cognitive work analysis
- Evaluation of different integrated burnable absorber materials in fuel assemblies of Bushehr WWER-1000 nuclear reactor
- Effective physical protection system design and implementation at a radiological facility: an integrated and risk management approach
- Determination of limiter design and material composition of MT-II spherical tokamak
- Dynamics effects of tritium reduction on the energy gain of D-T fuel pellet using double cone ignition
- Design of an unattended ore grading measurement system in a uranium mine
- Prediction of heat transfer characteristics in a microchannel with vortex generators by machine learning
- Prediction of nanofluid flows’ optimum velocity in finned tube-in-tube heat exchangers using artificial neural network
- Investigating the in-core 60Co production assembly for open pool type reactor
- Calendar of events
Artikel in diesem Heft
- Frontmatter
- Application of the COCOSYS code in the safety evaluation of Czech nuclear power plants
- Improving of electric network feeding nuclear facility based on multiple types DGs placement
- Design and evaluation of ecological interface for Feedwater Deaerating Tank and Gas Stripper System based on cognitive work analysis
- Evaluation of different integrated burnable absorber materials in fuel assemblies of Bushehr WWER-1000 nuclear reactor
- Effective physical protection system design and implementation at a radiological facility: an integrated and risk management approach
- Determination of limiter design and material composition of MT-II spherical tokamak
- Dynamics effects of tritium reduction on the energy gain of D-T fuel pellet using double cone ignition
- Design of an unattended ore grading measurement system in a uranium mine
- Prediction of heat transfer characteristics in a microchannel with vortex generators by machine learning
- Prediction of nanofluid flows’ optimum velocity in finned tube-in-tube heat exchangers using artificial neural network
- Investigating the in-core 60Co production assembly for open pool type reactor
- Calendar of events
