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The used nuclear fuels (produced in an open fuel cycle without reprocessing) considered in this work come from a Swiss Pressurised Water Reactor, taking into account their realistic lifetime in the reactor core and cooling periods, up to their disposal in the final geological repository. The case of 212 representative used nuclear fuel assemblies is analysed, assuming a loading of 4 fuel assemblies per canister, and optimizing two safety parameters: the fuel decay heat (DH) and the canister effective neutron multiplication factor <jats:italic>k<\/jats:italic><jats:inline-formula><jats:alternatives><jats:tex-math>$$_{\\mathrm{eff}}$$<\/jats:tex-math><mml:math xmlns:mml=\"http:\/\/www.w3.org\/1998\/Math\/MathML\">\n                  <mml:msub>\n                    <mml:mrow\/>\n                    <mml:mi>eff<\/mml:mi>\n                  <\/mml:msub>\n                <\/mml:math><\/jats:alternatives><\/jats:inline-formula>. In the present approach, a neural network is trained as a surrogate model to evaluate the <jats:italic>k<\/jats:italic><jats:inline-formula><jats:alternatives><jats:tex-math>$$_{\\mathrm{eff}}$$<\/jats:tex-math><mml:math xmlns:mml=\"http:\/\/www.w3.org\/1998\/Math\/MathML\">\n                  <mml:msub>\n                    <mml:mrow\/>\n                    <mml:mi>eff<\/mml:mi>\n                  <\/mml:msub>\n                <\/mml:math><\/jats:alternatives><\/jats:inline-formula> value to substitute the time-consuming-code Monte Carlo transport &amp; depletion SERPENT for specific canister loading calculations. A genetic algorithm is then developed to optimise simultaneously the canister <jats:italic>k<\/jats:italic><jats:inline-formula><jats:alternatives><jats:tex-math>$$_{\\mathrm{eff}}$$<\/jats:tex-math><mml:math xmlns:mml=\"http:\/\/www.w3.org\/1998\/Math\/MathML\">\n                  <mml:msub>\n                    <mml:mrow\/>\n                    <mml:mi>eff<\/mml:mi>\n                  <\/mml:msub>\n                <\/mml:math><\/jats:alternatives><\/jats:inline-formula> and DH values. The <jats:italic>k<\/jats:italic><jats:inline-formula><jats:alternatives><jats:tex-math>$$_{\\mathrm{eff}}$$<\/jats:tex-math><mml:math xmlns:mml=\"http:\/\/www.w3.org\/1998\/Math\/MathML\">\n                  <mml:msub>\n                    <mml:mrow\/>\n                    <mml:mi>eff<\/mml:mi>\n                  <\/mml:msub>\n                <\/mml:math><\/jats:alternatives><\/jats:inline-formula> computed during the optimisation algorithm is using the previously developed artificial neural network. The optimisation algorithm allows (1) to minimize the number of canisters, given assumed limits for both DH and <jats:italic>k<\/jats:italic><jats:inline-formula><jats:alternatives><jats:tex-math>$$_{\\mathrm{eff}}$$<\/jats:tex-math><mml:math xmlns:mml=\"http:\/\/www.w3.org\/1998\/Math\/MathML\">\n                  <mml:msub>\n                    <mml:mrow\/>\n                    <mml:mi>eff<\/mml:mi>\n                  <\/mml:msub>\n                <\/mml:math><\/jats:alternatives><\/jats:inline-formula> quantities and (2) to minimize DH and <jats:italic>k<\/jats:italic><jats:inline-formula><jats:alternatives><jats:tex-math>$$_{\\mathrm{eff}}$$<\/jats:tex-math><mml:math xmlns:mml=\"http:\/\/www.w3.org\/1998\/Math\/MathML\">\n                  <mml:msub>\n                    <mml:mrow\/>\n                    <mml:mi>eff<\/mml:mi>\n                  <\/mml:msub>\n                <\/mml:math><\/jats:alternatives><\/jats:inline-formula> differences among canisters. This study represents a proof-of-principle of the neural network and genetic algorithm capabilities, and will be applied in the future to a larger number of cases.<\/jats:p>","DOI":"10.1007\/s00521-021-06258-2","type":"journal-article","created":{"date-parts":[[2021,7,4]],"date-time":"2021-07-04T11:02:10Z","timestamp":1625396530000},"page":"16627-16639","update-policy":"https:\/\/doi.org\/10.1007\/springer_crossmark_policy","source":"Crossref","is-referenced-by-count":22,"title":["Optimisation of used nuclear fuel canister loading using a neural network and genetic algorithm"],"prefix":"10.1007","volume":"33","author":[{"ORCID":"https:\/\/orcid.org\/0000-0001-6839-3435","authenticated-orcid":false,"given":"Virginie","family":"Solans","sequence":"first","affiliation":[]},{"given":"Dimitri","family":"Rochman","sequence":"additional","affiliation":[]},{"given":"Christian","family":"Brazell","sequence":"additional","affiliation":[]},{"given":"Alexander","family":"Vasiliev","sequence":"additional","affiliation":[]},{"given":"Hakim","family":"Ferroukhi","sequence":"additional","affiliation":[]},{"given":"Andreas","family":"Pautz","sequence":"additional","affiliation":[]}],"member":"297","published-online":{"date-parts":[[2021,7,4]]},"reference":[{"key":"6258_CR1","unstructured":"(2008) Sectoral Plan for deep geological repositories\u2014conceptual Part 2008, swiss federal office of energy, Switzerland, available here"},{"key":"6258_CR2","unstructured":"(2016) The Nagra research, development and demonstration (RD&D) plan for the disposal of radioactive waste in Switzerland, NAGRA technical report 16\u201302"},{"key":"6258_CR3","unstructured":"Amann F, L\u00f6w S, Perras M (2015) Assessment of geomechanical properties, maximum depth below ground surface and EDZ impact on long term safety\u201d, ETH Z\u00fcrich, October 29, , ENSI Report No. 33\/460"},{"key":"6258_CR4","unstructured":"(2009) The Nagra research, development and demonstration (RD&D) plan for the disposal of radioactive waste in Switzerland, NAGRA technical report 09\u201306"},{"key":"6258_CR5","unstructured":"(2015) Spent nuclear fuel management in Switzerland. 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