Dry cask radiation shielding validation and estimation of cask surface dose rate with MAVRIC during long-term storage

Gao, Yuan; McFerran, Noah; Enqvist, Andreas; Tulenko, James; Baciak, James E.

doi:10.1016/j.anucene.2019.107145

Cited by 14 publications

(2 citation statements)

References 11 publications

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“…Some results on dose rate evaluations for extended storage periods were performed and presented in [12]. Similar evaluations for extended storage of TN-32 container containing other types of SF were provided in [13]. It should be emphasized that the typical design lifetime of dry storage containers is 40-60 years.…”

Section: Introductionmentioning

confidence: 96%

Comparison of Gamma and Neutron Dose Rate Variations with Time for Cast Iron and Metal–Concrete Casks Used for RBMK-1500 Spent Fuel Storage

et al. 2021

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The present SF management concept in Lithuania envisages that spent RBMK-1500 fuel will be stored in dry storage containers for 50 years, before being disposed of in a deep geological repository. However, the risk that a deep geological repository will not be constructed at the planned time should be taken into account, and the extension of SF storage over 50 years should be considered. This paper presents a comparison of gamma and neutron dose rate distributions and variations with planned and extended storage times for cast iron and metal–concrete containers loaded with RBMK-1500 SF. All calculations were performed using the SCALE computer codes system. The modeling results show that the overall shielding properties of the CONSTOR® RBMK-1500 container containing the same neutron and gamma sources are better than those of the CASTOR® RBMK-1500 container. During an extended storage period (from 50 to 300 years), the total dose rate would decrease considerably and the dose rate due to neutrons would become dominant for both containers.

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Section: Introductionmentioning

confidence: 96%

Comparison of Gamma and Neutron Dose Rate Variations with Time for Cast Iron and Metal–Concrete Casks Used for RBMK-1500 Spent Fuel Storage

et al. 2021

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“…Entre otros temas estudiados, también podemos encontrar investigaciones sobre la dosis asociada al contenedor TN-32 mediante modelos numéricos y llegando hasta los 300 años de vida del contenedor (Gao et al, 2020), estudios mecánicos (Feria et al, , 2015 estudios para la optimización de la carga de los contenedores (Spencer et al, 2018), estudios de vibración (Lin et al, 2020), análisis frente a cargas sísmicas (Ebad Sichani et al, 2018) e incluso sobre la interacción de los muones presentes en los rayos cósmicos con los contenedores (Chatzidakis et al, 2016).…”

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Metodología para el desarrollo de modelos de contenedores de combustible nuclear gastado mediante el código Ansys CFX

Avellaneda¹

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The management of spent fuel has always been one of the challenges in the nuclear power operation and generation. In some of the nuclear power plants in operation, the available space in the spent fuel pool it is reaching the limit, therefore spent fuel needs to be stored using dry storage options.As a frequent dry storage option, the nuclear spent fuel casks can be highlighted. Numerous nuclear power plants both in the world and in Spain already have independent spent fuel storage installations, where the spent fuel casks are stored. These installations are considered absolutely necessary both for the continuity of the nuclear power plants once they have reached their spent fuel pool capacity, and during the decommissioning phase.

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Advancements in shielding materials for spent fuel storage

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Thomas

Rico

et al. 2020

Micro and Nanostructured Composite Materials for Neutron Shielding Applications

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Dry cask radiation shielding validation and estimation of cask surface dose rate with MAVRIC during long-term storage

Cited by 14 publications

References 11 publications

Comparison of Gamma and Neutron Dose Rate Variations with Time for Cast Iron and Metal–Concrete Casks Used for RBMK-1500 Spent Fuel Storage

Comparison of Gamma and Neutron Dose Rate Variations with Time for Cast Iron and Metal–Concrete Casks Used for RBMK-1500 Spent Fuel Storage

Metodología para el desarrollo de modelos de contenedores de combustible nuclear gastado mediante el código Ansys CFX

Advancements in shielding materials for spent fuel storage

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