A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage Casks

The management of spent nuclear fuel assemblies of nuclear reactors is a priority subject among member states of the International Atomic Energy Agency. For the majority of these countries, the destination of such fuel assemblies is a decision that is yet to be made and the “wait-and-see” policy is...

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Main Authors: Ian B. Gomes, Pedro L. Cruz Saldanha, Antonio Carlos M. Alvim
Format: Article
Language:English
Published: Hindawi Limited 2019-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2019/4309545
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spelling doaj-32a7d86d9c504d87b332689f23746c632020-11-24T21:56:46ZengHindawi LimitedScience and Technology of Nuclear Installations1687-60751687-60832019-01-01201910.1155/2019/43095454309545A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage CasksIan B. Gomes0Pedro L. Cruz Saldanha1Antonio Carlos M. Alvim2COPPE, Programa de Engenharia Nuclear, Universidade Federal do Rio de Janeiro, UFRJ, 21941-914, BrazilCGRC/DRS, Comissão Nacional de Energia Nuclear, 22290-901, BrazilCOPPE, Programa de Engenharia Nuclear, Universidade Federal do Rio de Janeiro, UFRJ, 21941-914, BrazilThe management of spent nuclear fuel assemblies of nuclear reactors is a priority subject among member states of the International Atomic Energy Agency. For the majority of these countries, the destination of such fuel assemblies is a decision that is yet to be made and the “wait-and-see” policy is thus adopted by them. In this case, the irradiated fuel is stored in on-site spent fuel pools until the power plant is decommissioned or, when there is no more racking space in the pool, they are stored in intermediate storage facilities, which can be another pool or dry storage systems, until the final decision is made. The objective of this study is to propose a methodology that, using optimization algorithms, determines the ideal time for removal of the fuel assemblies from the spent fuel pool and to place them into dry casks for intermediate storage. In this scenario, the methodology allows for the optimal dimensioning of the designed spent fuel pools and the casks’ characteristics, thus reducing the final costs for purchasing new Nuclear Power Plants (NPP), as the size and safety features of the pool could be reduced and dry casks, that would be needed anyway after the decommissioning of the plant, could be purchased with optimal costs. To demonstrate the steps involved in the proposed methodology, an example is given, one which uses the Monte Carlo N-Particle code (MCNP) to calculate the shielding requirements for a simplified model of a concrete dry cask. From the given example, it is possible to see that, using real-life data, the proposed methodology can become a valuable tool to help making nuclear energy a more attractive choice costwise.http://dx.doi.org/10.1155/2019/4309545
collection DOAJ
language English
format Article
sources DOAJ
author Ian B. Gomes
Pedro L. Cruz Saldanha
Antonio Carlos M. Alvim
spellingShingle Ian B. Gomes
Pedro L. Cruz Saldanha
Antonio Carlos M. Alvim
A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage Casks
Science and Technology of Nuclear Installations
author_facet Ian B. Gomes
Pedro L. Cruz Saldanha
Antonio Carlos M. Alvim
author_sort Ian B. Gomes
title A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage Casks
title_short A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage Casks
title_full A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage Casks
title_fullStr A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage Casks
title_full_unstemmed A Methodology for Optimizing the Management of Spent Fuel of Nuclear Power Plants Using Dry Storage Casks
title_sort methodology for optimizing the management of spent fuel of nuclear power plants using dry storage casks
publisher Hindawi Limited
series Science and Technology of Nuclear Installations
issn 1687-6075
1687-6083
publishDate 2019-01-01
description The management of spent nuclear fuel assemblies of nuclear reactors is a priority subject among member states of the International Atomic Energy Agency. For the majority of these countries, the destination of such fuel assemblies is a decision that is yet to be made and the “wait-and-see” policy is thus adopted by them. In this case, the irradiated fuel is stored in on-site spent fuel pools until the power plant is decommissioned or, when there is no more racking space in the pool, they are stored in intermediate storage facilities, which can be another pool or dry storage systems, until the final decision is made. The objective of this study is to propose a methodology that, using optimization algorithms, determines the ideal time for removal of the fuel assemblies from the spent fuel pool and to place them into dry casks for intermediate storage. In this scenario, the methodology allows for the optimal dimensioning of the designed spent fuel pools and the casks’ characteristics, thus reducing the final costs for purchasing new Nuclear Power Plants (NPP), as the size and safety features of the pool could be reduced and dry casks, that would be needed anyway after the decommissioning of the plant, could be purchased with optimal costs. To demonstrate the steps involved in the proposed methodology, an example is given, one which uses the Monte Carlo N-Particle code (MCNP) to calculate the shielding requirements for a simplified model of a concrete dry cask. From the given example, it is possible to see that, using real-life data, the proposed methodology can become a valuable tool to help making nuclear energy a more attractive choice costwise.
url http://dx.doi.org/10.1155/2019/4309545
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