Transmutation technology has been developed to address the issue of long-term safety of nuclear waste disposal in geological repository. Transuranic (TRU) transmutation in thermal neutron spectrum can be considered more beneficial at the present time due to the larger fission cross section of TRU elements than in fast neutron spectrum. This paper discusses preliminary study on TRU transmutation in Vodo-Vodyanoi Energetichesky Reactor (VVER)-1000 fuel assembly using MCNP6 code. The fuel assembly is configured by 312 fuel cells consist of 300 UO2 fuel rods with 3.7 wt% 235U and 12 UGD fuel rods containing a mixture of UO2 with 3.6 wt% 235U and 4.0 wt% Gd2O3. The calculation results show that the k inf value is higher with the increase in the TRU thickness at the beginning of cycle and at the end of cycle, which means that the addition of TRU will increase the fuel cycle length. The total temperature coefficient of reactivity is negative for all fuel assemblies both without TRU and with TRU. In general, the computed β eff values of the assembly with and without TRU addition are not significantly different. It shows that the coating of the TRU layer in the UGD fuel cell will not complicate the reactor control. The transmutation of TRU recycled from spent nuclear fuel in the VVER-1000 fuel assembly can be considered feasible from the viewpoint of excess reactivity and control safety characteristics. The total transmutation rate of ∼55.73% can be achieved with 239Pu and 241Am isotopes are taking the largest portion of transmuted nuclides.
The authors would like to express gratitude to Dr. Ir. M. Dhandhang Purwadi, MT. and Syaiful Bakhri, Ph.D. who gave the permission for this research collaboration.
Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
Research funding: None declared.
Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
Carter, J.P. and Borrelli, R.A. (2020). Integral molten salt reactor neutron physics study using Monte Carlo n-particle code. Nucl. Eng. Des. 365: 110718, https://doi.org/10.1016/j.nucengdes.2020.110718.Search in Google Scholar
Chadwick, M.B., Obložinský, P., Herman, M., Greene, N.M., McKnight, R.D., Smith, D.L., Young, P.G., MacFarlane, R.E., Hale, G.M., Frankle, S.C., et al.. (2006). ENDF/B-VII: next generation evaluated nuclear data library for nuclear science and technology. Nucl. Data Sheets 107: 2931–3060, https://doi.org/10.1016/j.nds.2006.11.001.Search in Google Scholar
Facchini, A., Giusti, V., Ciolini, R., Tuček, K., Thomas, D., and D’Agata, E. (2017). Detailed neutronic study of the power evolution for the European sodium fast reactor during a positive insertion of reactivity. Nucl. Eng. Des. 313: 1–9, https://doi.org/10.1016/j.nucengdes.2016.11.014.Search in Google Scholar
Goorley, J.T., James, M.R., Booth, T.E., Brown, F.B., Bull, J.S., Cox, L.J., Durkee Jr, J.W., Elson, J.S., Fensin, M.L., Forster III, R.A., et al.. (2013). Initial MCNP6 release overview – MCNP6 version 1.0. LA-UR-13-22934, Los Alamos National Laboratory.10.2172/1086758Search in Google Scholar
Hyland, B. and Dyck, G.R. (2007). Actinide burning in CANDU reactors. In: Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems, Boise, Idaho, USA, 9–13 September 2007, 1201–1204.Search in Google Scholar
International Atomic Energy Agency (2007). Estimation of global inventories of radioactive waste and other radioactive materials. IAEA-TECDOC-1591.Search in Google Scholar
International Atomic Energy Agency (2009). Status of minor actinide fuel development. IAEA Nuclear Energy Series No. NF-T-4.6.Search in Google Scholar
International Atomic Energy Agency (2019). Waste from innovative types of reactors and fuel cycle: a preliminary study. IAEA Nuclear Energy Series No. NW-T-1.7.Search in Google Scholar
Kalugin, M., Shkarovsky, D., Gehin, J., Hesketh, K., and Sartori, E. (2002). A VVER-1000 LEU and MOX assembly computational Benchmark. NEA/NSC/DOC(2002)10, Nuclear Energy Agency Organisation for Economic Co-operation and Development.Search in Google Scholar
Liem, P.H., Zuhair, and Hartanto, D. (2019). Sensitivity and uncertainty analysis on the first core criticality of the RSG GAS multipurpose research reactor. Prog. Nucl. Energy 114: 46–60, https://doi.org/10.1016/j.pnucene.2019.03.001.Search in Google Scholar
Poinssot, Ch. and Boullis, B. (2012). Actinide recycling within closed fuel cycles. Nucl. Eng. Int. 57: 17–21.Search in Google Scholar
Read, C.M.Jr., Knight, T.W., and Allen, K.S. (2011). Using a modified CINDER90 routine in MCNPX 2.6.0 for the prediction of helium production in minor actinide targets. Nucl. Eng. Des. 241: 5033–5038.10.1016/j.nucengdes.2011.09.016Search in Google Scholar
Schmidt, O.V., Makeeva, I.R., and Liventsov, S.N. (2016). Modeling closed nuclear fuel cycle processes. Procedia Chem. 21: 503–508, https://doi.org/10.1016/j.proche.2016.10.070.Search in Google Scholar
Tran, H.N., Hoang, V.K., Liem, P.H., and Hoang, H.T.P. (2019). Neutronics design of VVER-1000 fuel assembly with burnable poison particles. Nucl. Eng. Technol. 51: 1729–1737, https://doi.org/10.1016/j.net.2019.05.026.Search in Google Scholar
Zuhair, Suwoto, Setiadipura, T., and Su’ud, Z. (2020). Study on MCNP6 model in the calculation of kinetic parameters for pebble bed reactor. Acta Polytech. 60: 175–184, https://doi.org/10.14311/AP.2020.60.0175.Search in Google Scholar
Zuhair, Suwoto, Setiadipura, T., and Kuijper, J.C. (2019a). Study on the characteristics of effective delayed neutron fraction (βeff) for pebble-bed reactor with plutonium fuel. Iran. J. Sci. Technol. Trans. A Sci.: 1–9, https://doi.org/10.1007/s40995-019-00772-8.Search in Google Scholar
Zuhair, Suwoto, Setiadipura, T., and Kuijper, J.C. (2019b). The effects of fuel type on control rod reactivity of pebble-bed reactor. Nukleonika 64: 131–138, https://doi.org/10.2478/nuka-2019-0017.Search in Google Scholar
Zuhair, Suwoto, Permana, S., and Setiadipura, T. (2021a). Study on control rod reactivity of small pebble bed reactor with wallpaper fuel design. J. Phys. Conf. 1772: 012021, https://doi.org/10.1088/1742-6596/1772/1/012021.Search in Google Scholar
Zuhair, Dwijayanto, R.A.P., Suwoto, and Setiadipura, T. (2021b). The implication of thorium fraction on neutronic parameters of pebble bed reactor. Kuwait J. Sci. 48: 1–16, https://doi.org/10.48129/kjs.v48i3.9984.Search in Google Scholar
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