Numerical modelling of modular high-temperature gas-cooled reactors with thorium fuel

1 Talamo, A., Ji, W., Cetnar, J., & Gudowski, W. (2006). Comparison of MCB and MONTEBURNS Monte Carlo burnup codes on a one-pass deep burn. Ann. Nucl. Energy, 33(14/15), 1176–1188. doi.org/10.1016/j.anucene.2006.08.006. TalamoA. JiW. CetnarJ. GudowskiW. 2006 Comparison of MCB and MONTEBURNS Monte Carlo burnup codes on a one-pass deep burn Ann. Nucl. Energy 33 14/15 1176 1188 doi.org/10.1016/j.anucene.2006.08.006. 10.1016/j.anucene.2006.08.006 Search in Google Scholar

2 International Atomic Energy Agency. (2012). Role of thorium to supplement fuel cycles of future nuclear energy systems. Vienna: IAEA. (Nuclear Energy Series NF-T-2.4). International Atomic Energy Agency 2012 Role of thorium to supplement fuel cycles of future nuclear energy systems Vienna IAEA (Nuclear Energy Series NF-T-2.4). Search in Google Scholar

3 International Atomic Energy Agency. (2005). Thorium fuel cycle – Potential benefits and challenges. Vienna: IAEA. (IAEA-TECDOC-1450). International Atomic Energy Agency 2005 Thorium fuel cycle – Potential benefits and challenges Vienna IAEA (IAEA-TECDOC-1450). Search in Google Scholar

4 Shamanin, I. V., Grachev, V. M., Chertkov, Yu. B., Bedenko, S. V., Mendoza, O., & Knyshev, V. V. (2018). Neutronic properties of high-temperature gas-cooled reactors with thorium fuel. Ann. Nucl. Energy, 113, 286–293. DOI: 10.1016/j.anucene.2017.11.045. ShamaninI. V. GrachevV. M. ChertkovYu. B. BedenkoS. V. MendozaO. KnyshevV. V. 2018 Neutronic properties of high-temperature gas-cooled reactors with thorium fuel Ann. Nucl. Energy 113 286 293 10.1016/j.anucene.2017.11.045 Open DOISearch in Google Scholar

5 Oettingen, M., & Stanisz, P. (2018). Monte Carlo modelling of Th-Pb fuel assembly with californium neutron source. Nukleonika, 63(3), 87–91. DOI: 10.2478/nuka-2018-0011. OettingenM. StaniszP. 2018 Monte Carlo modelling of Th-Pb fuel assembly with californium neutron source Nukleonika 63 3 87 91 10.2478/nuka-2018-0011 Open DOISearch in Google Scholar

6 Cetnar, J. (2006). Solution of Bateman equations for nuclear transmutations. Ann. Nucl. Energy, 33, 640–645. DOI: 10.1016/j.anucene.2006.02.004. CetnarJ. 2006 Solution of Bateman equations for nuclear transmutations Ann. Nucl. Energy 33 640 645 10.1016/j.anucene.2006.02.004 Open DOISearch in Google Scholar

7 Oettingen, M., Cetnar, J., & Mirowski, T. (2015). The MCB code for numerical modelling of fourth generation nuclear reactors. Computer Science, 16, 329–350. DOI: 10.7494/csci.2015.16.4.329. OettingenM. CetnarJ. MirowskiT. 2015 The MCB code for numerical modelling of fourth generation nuclear reactors Computer Science 16 329 350 10.7494/csci.2015.16.4.329 Open DOISearch in Google Scholar

8 Cetnar, J., Stanisz, P., & Oettingen, M. (2021). Linear chain method for numerical modelling of burnup systems. Energies, 14, 1520. https://doi.org/10.3390/en14061520. CetnarJ. StaniszP. OettingenM. 2021 Linear chain method for numerical modelling of burnup systems Energies 14 1520 https://doi.org/10.3390/en14061520. 10.3390/en14061520 Search in Google Scholar

9 Oettingen, M. (2021). Assessment of the radiotoxicity of spent nuclear fuel from a fleet of PWR reactors (2021). Energies, 14, 3094. https://doi.org/10.3390/en14113094. OettingenM. 2021 Assessment of the radiotoxicity of spent nuclear fuel from a fleet of PWR reactors (2021) Energies 14 3094 https://doi.org/10.3390/en14113094. 10.3390/en14113094 Search in Google Scholar