The Evaluation of Minimum Cooling Period for Loading of PWR Spent Nuclear Fuel of a Dual Purpose Metal Cask

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

doi:10.7733/jnfcwt.2016.14.4.411

Cited by 5 publications

(2 citation statements)

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“…The principal size constraints on the core, internal structures, and primary vessel are imposed by the capacity of commercial transportation casks licensed for spent nuclear fuel. The MicroURANUS cask design concept adapts the KORAD‐21 design under development by the Korea radioactive waste agency (KORAD) 31 . The current pre‐conceptual cask design developed specifically for MicroURANUS was performed by Moojin, Ltd., 32 a KORAD partner that owns the intellectual property of KORAD‐21 cask through a technology transfer agreement.…”

Section: Design Objectives and Constraintsmentioning

confidence: 99%

MicroURANUS : Core design for long‐cycle lead‐bismuth‐cooled fast reactor for marine applications

et al. 2021

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Summary A core design of MicroURANUS, a long‐cycle lead‐bismuth‐cooled fast nuclear reactor for marine applications, is presented. It aims to generate a power of 60MWth, which can be regulated during operation. MicroURANUS was designed to achieve a small burnup reactivity swing for 30 effective full‐power years of a lifetime without refueling. To attain these goals, a unit cell study with uranium oxide fuel was initiated to lay a solid foundation for core design, owing to size constraints. A reflector optimization was also performed to minimize neutron leakage. MicroURANUS adopts onion zoning constructed by two enrichment zones for flattening the power and lengthening the core lifetime. The coolant is driven by electromagnetic pumps to achieve inlet and outlet temperatures of 250°C and 350°C, respectively. MicroURANUS analyses were performed using the Argonne Reactor Computation suite and the Monte Carlo code MCS. Core performance features were analyzed for criticality, power profiles, fuel isotope mass inventory, reflector coefficients, reactivity feedback coefficients, and shutdown margin. Additional thermal‐hydraulic calculations were performed to confirm that the fuel and cladding temperatures were within the acceptable range. Furthermore, a load follow analysis using the quasi‐static reactivity balance method confirmed the feasibility of regulating power by adjusting the inlet coolant temperature.

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Section: Design Objectives and Constraintsmentioning

confidence: 99%

MicroURANUS : Core design for long‐cycle lead‐bismuth‐cooled fast reactor for marine applications

et al. 2021

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“…Both the initial enrichment of 235 U of nuclear fuel and its resulting burnup affect the neutron source terms in SNF as implied in Equation ( 3), however, the two parameters are generally proportional to each other; that is, the nuclear fuel with higher initial enrichment is usually irradiated longer in the reactor core and then discharged as SNF with higher burnup. However, the spent nuclear fuels are actually discharged from the reactor core after various burning times in accordance with the planned loading plans or due to an unplanned event [50]. Accordingly, the neutron source terms in the SNF to be stored were calculated at 4.2 wt% of the reference fuel enrichment but by varying the fuel burnup from 35 to 70 GWD/MTU at every 5 GWD/MTU using the ORIGEN-ARP code (see Step 1 in Figure 2).…”

Section: Effect Of Fuel Burnupmentioning

confidence: 99%

Neutron Activation of Structural Materials of a Dry Storage System for Spent Nuclear Fuel and Implications for Radioactive Waste Management

Lee

Cheong

2020

Energies

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In order to estimate the radiological characteristics of disused dry storage systems for spent nuclear fuel, a stepwise framework to calculate neutron sources (ORIGEN-ARP), incident neutron flux and reaction rate (MCNPX), effective cross-section (hand calculation), and residual activity (ORIGEN-2) was established. Applicability of the framework was demonstrated by comparing the residual activity of a commercialized storage system, HI-STORM 100, listed in the safety analysis report and calculated in this study. For a reference case assuming an impurity-free storage system, the modified effective cross-sections were theoretically interpreted and the need for managing disused components as a radioactive waste for at least four years was demonstrated. Sensitivity analyses showed that the higher burnup induces the higher residual radioactivity, and the impurity 59Co may extend the minimum decay-in-storage period up to 51 years within the reported range of 59Co content in stainless steel. The extended long-term storage over 100 years, however, caused no significant increase in residual radioactivity. Impurity control together with appropriate decay-in-storage was proposed as an effective approach to minimize the secondary radioactive waste arising from disused dry storage systems. The results of this study could be used to optimize the decommissioning and waste management plan regarding interim storage of spent fuel.

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Multi-body dynamics model for spent nuclear fuel transportation system under normal transport test conditions

Han

Jeong

Lee

et al. 2023

Nuclear Engineering and Technology

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The Evaluation of Minimum Cooling Period for Loading of PWR Spent Nuclear Fuel of a Dual Purpose Metal Cask

Cited by 5 publications

References 0 publications

MicroURANUS : Core design for long‐cycle lead‐bismuth‐cooled fast reactor for marine applications

MicroURANUS : Core design for long‐cycle lead‐bismuth‐cooled fast reactor for marine applications

Neutron Activation of Structural Materials of a Dry Storage System for Spent Nuclear Fuel and Implications for Radioactive Waste Management

Multi-body dynamics model for spent nuclear fuel transportation system under normal transport test conditions

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