Preliminary Shielding Analysis of the Concrete Cask for Spent Nuclear Fuel Under Dry Storage Conditions

Kim, Tae-Man; Dho, Ho-Seog; Cho, Chun-Hyung; Ko, Jae-Hun

doi:10.7733/jnfcwt.2017.15.4.391

Cited by 4 publications

(1 citation statement)

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“…In this approach, spent fuel is stored in specialized facilities until its radioactivity reduces sufficiently for reprocessing [ 6 ]. The safe transportation of this spent fuel requires specialized casks designed to shield against radioactivity which incorporate multiple layers of materials such as steels, lead, concretes, and polymers [ 7 , 8 , 9 ]. However, the loading capacity of these specialized casks is much lower than that of traditional containers.…”

Section: Introductionmentioning

confidence: 99%

Long-Service-Life Rigid Polyurethane Foam Fillings for Spent Fuel Transportation Casks

Zhang,

Shen,

et al. 2024

Polymers

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Soft materials bearing rigid, lightweight, and vibration-dampening properties offer distinct advantages over traditional wooden and metal-based fillings for spent fuel transport casks, due to their low density, tunable structure, excellent mechanical properties, and ease of processing. In this study, a novel type of rigid polyurethane foam is prepared using a conventional polycondensation reaction between isocyanate and hydroxy groups. Moreover, the density and size of the pores in these foams are precisely controlled through simultaneous gas generation. The as-prepared polyurethane exhibits high thermal stability exceeding 185 °C. Lifetime predictions based on thermal testing indicate that these polyurethane foams could last up to over 60 years, which is double the lifetime of conventional materials of about 30 years. Due to their occlusive structure, the mechanical properties of these polymeric materials meet the design standards for spent fuel transport casks, with maximum compression and tensile stresses of 6.89 and 1.37 MPa, respectively, at a testing temperature of −40 °C. In addition, these polymers exhibit effective flame retardancy; combustion ceased within 2 s after removal of the ignition source. All in all, this study provides a simple strategy for preparing rigid polymeric foams, presenting them as promising prospects for application in spent fuel transport casks.

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Section: Introductionmentioning

confidence: 99%

Long-Service-Life Rigid Polyurethane Foam Fillings for Spent Fuel Transportation Casks

Zhang,

Shen,

et al. 2024

Polymers

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The Advancement of Neutron-Shielding Materials for the Transportation and Storage of Spent Nuclear Fuel

Yang

et al. 2022

Materials

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In this paper, the mechanism of neutron absorption and common reinforced particles is introduced, and recent research progress on different types of neutron-shielding materials (borated stainless steels, B/Al Alloy, B4C/Al composites, polymer-based composites, and shielding concrete) for transportation and wet or dry storage of spent fuel is elaborated, and critical performance is summarized and compared. In particular, the most widely studied and used borated stainless steel and B4C/Al composite neutron-absorption materials in the field of spent fuel are discussed at length. The problems and solutions in the preparation and application of different types of neutron-shielding materials for spent fuel transportation and storage are discussed, and their research priorities and development trends are proposed.

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Some aspects of the use of steel during out of reactor storage and transportation of spent nuclear fuel. (Review)

Balakhanova,

Chuiko,

Parusov

et al. 2023

Fund.Appl.Probl.F.Met

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In the world, the nuclear industry is considered an ideal option for an environmentally friendly source of energy generation, based on the separation of the radioactive nuclide of the chemical element 235U. When generating electricity from nuclear power plants, the main disadvantage is the generation of radioactive waste. After spent fuel is removed from a nuclear reactor, it is placed in special containers containing absorption and retention elements. It is obvious that the storage and transportation of spent nuclear fuel plays an important role in the development and overall safety of the nuclear industry, and high-quality neutron-absorbing materials are the basis for the successful manufacture of reliable structures and containers. The development of modern neutron absorption materials ensures reliability, safety, storage duration, as well as reducing the cost of logistics operations associated with the transportation of radioactive waste. Based on the results of the analysis of scientific and technical sources, modern ideas about materials for the manufacture of containers, which are used for storage and transportation of nuclear fuel waste, are summarized. The advantages and disadvantages of the main materials used in the disposal of spent nuclear fuel are considered. It has been established that, from an economic point of view, the most rational material for storing and transporting radioactive waste is ferritic stainless steel with a high boron content, which, in addition to absorption abilities, is characterized by other properties required for this type of product. Since boron has a low ability to dissolve in both austenite and ferrite, this leads to the formation of borides of various types, which contribute to the embrittlement of the structural material. At the same time, the distribution of borides over the volume of a metal product is determined not only by a set of properties, but also by the protective properties of the material, as well as the manufacturability of the final product from it. Despite the fact that boron-containing steels of the ferritic class have been known for a long time, issues related to the processes of structure formation, increasing technological and operational properties still remain insufficiently studied and controversial. There is also no information on the influence of heat treatment on the formation of the structure and mechanical properties of finished products made of ferritic stainless steels. Successful solution of these scientific and technical problems will ensure the production of modern high-quality neutron-absorbing containers for off-reactor storage and transportation of spent nuclear fuel.

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Preliminary Shielding Analysis of the Concrete Cask for Spent Nuclear Fuel Under Dry Storage Conditions

Cited by 4 publications

References 0 publications

Long-Service-Life Rigid Polyurethane Foam Fillings for Spent Fuel Transportation Casks

Long-Service-Life Rigid Polyurethane Foam Fillings for Spent Fuel Transportation Casks

The Advancement of Neutron-Shielding Materials for the Transportation and Storage of Spent Nuclear Fuel

Some aspects of the use of steel during out of reactor storage and transportation of spent nuclear fuel. (Review)

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