Preliminary three-dimensional neutronic analysis of IFBA coated TRISO fuel particles in prismatic-core advanced high temperature reactor

Alameri, Saeed A.; Alrwashdeh, Mohammad

doi:10.1016/j.anucene.2021.108551

Cited by 16 publications

(6 citation statements)

References 14 publications

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“…The one-sided tolerance-limit factor (t f n β/γ1 ) with a 95% probability and 95% confidence level is chosen to determine the k eff bias uncertainty in Equation ( 10): (10) The bias and bias uncertainty in the k eff resulting from isotopic bias and bias uncertainty can then be expressed as follows:…”

Section: Uncertainty Sampling Methodsmentioning

confidence: 99%

“…Light-water reactors (LWRs) are dominant around the world [7,8], including Generation II and Generation III pressurized-water reactors (PWRs) and boiling-water reactors (BWRs) [9]. Some of the Generation IV plants include high-temperature gas-cooled reactors and molten-salt reactors [10,11]. Nuclear power plants produce accumulated minor actinides (MAs) and long-lived fission products (LLFPs) during operation.…”

Section: Introductionmentioning

confidence: 99%

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Quantitative Analysis Study of Effects of Nuclide Concentration Uncertainties on Biases and Bias Uncertainties in Criticality Calculation Method

Ni,

Chen,

Xie

et al. 2023

Energies

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To quantify the uncertainties propagating from the fuel depletion calculation to the criticality calculation in the burnup credit system, this paper evaluates the effects of the nuclide concentration uncertainty on the criticality calculation based on Monte Carlo uncertainty sampling methods, and analyzes the assumption that the measured-to-calculated nuclide concentration ratio obeys a normal distribution with uncorrelation among isotopes in the Monte Carlo uncertainty sampling method by using the sensitivity and uncertainty analysis method and the Latin hypercube sampling method. The results indicated that the Monte Carlo uncertainty sampling method could effectively quantify the uncertainties with a calculation accuracy within 3%, and the criticality uncertainty calculation for the assumption that the measured-to-calculated concentration ratios obey normal distributions was more conservative than that of the samples according to their actual distributions. Thus, the assumption of a normal distribution is reasonable in the sampling process. Moreover, the uncertainty results of the criticality calculation considering the correlations among important isotopes presented a decrease of approximately 5% over those without the isotopic correlations. Therefore, introducing the correlations of significant isotopes could reduce the uncertainty of the criticality calculation for spent-nuclear-fuel storage systems.

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Section: Uncertainty Sampling Methodsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Quantitative Analysis Study of Effects of Nuclide Concentration Uncertainties on Biases and Bias Uncertainties in Criticality Calculation Method

Ni,

Chen,

Xie

et al. 2023

Energies

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show abstract

“…To solve this problem, many treatment methods have been proposed and applied to reactor core physical analysis. For example, Alameri et al analyzed the effect of integral fuel burnable absorber (IFBA) coated the tri-structural isotropic (TRISO) on prismatic-core advanced high temperature reactor by collision of probability calculation method (Alameri and Alrwashdeh, 2021;Alrwashdeh et al, 2020). In addition, the RPT method is also an extension of the VHM and it has been proved to be effective in burnup calculation for DH system (Alrwashdeh et al, 2019).…”

Section: Introductionmentioning

confidence: 99%

An improved optical length research on the physical boundary of particle-dispersed fuel

Liu,

Chen,

et al. 2024

Front. Energy Res.

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The Volumetric Homogenization Method (VHM) is one of the most commonly used methods for neutronics calculation in reactors or components. However, the use of VHM for the Double-Heterogeneous (DH) System may lead to a large deviation in reactivity calculation. The deviation of DH System using the VHM can be expressed by the theoretically modified optical length. When the theoretically modified optical length is less than 10−4, the deviation caused by the VHM will be less than 100 pcm. This paper points out that the existing theoretically modified optical length for some cases of DH systems is not accurate, and this method is only for pin cell. In this paper, by calculating a series of DH models and their corresponding VHM models, it is found that the water-uranium ratio and the shape of fuel region seriously affects the reactivity calculation deviation of particle-dispersed fuel, the original modified optical length does not take this into account, resulting in unacceptable errors. On this basis, the application of optical length to physical boundaries for DH system is further discussed and the shape correction factor is taken into consideration. Therefore, an improved optical length is proposed, which greatly expands the range of application of the physical boundary judgment methods for the double heterogeneity of dispersed particle fuel. The numerical results show that the accuracy of the improved optical length in defining the physical boundary of double heterogeneous system is higher than the theoretically modified optical length.

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“…HTRs also offer inherent safety features, such as passive cooling and the ability to withstand higher temperatures without the risk of fuel melting. However, HTRs have limited operational experience and require specialized fuel in the form of TRISO particles, which can pose challenges in terms of fuel fabrication and availability [8].…”

Section: Introductionmentioning

confidence: 99%

Small Modular Reactors (SMRs) as a Solution for Renewable Energy Gaps: Spatial Analysis for Polish Strategy

Zarębski,

Katarzyński

2023

Energies

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The integration of Small Modular Reactors (SMRs) into energy systems requires a meticulous assessment of various factors, spanning renewable energy potential, legal frameworks, technical considerations, community engagement, and consumer preferences. This article synthesizes a multifaceted discussion on the subject, focusing on the need for comprehensive analyses before deciding to implement SMRs. Drawing insights from geographic information systems (GIS) and lessons from renewable energy development in Poland, this paper underscores the significance of aligning energy strategies with local needs, emphasizing stakeholder participation. This study examines the factors influencing location attractiveness for various energy technologies, including small modular nuclear reactors (SMRs), wind, solar, and hydroelectric power plants, within Poland. Employing 17 indicators sourced from Statistics Poland and URE, coupled with the application of the k-means algorithm, we outline four distinct clusters that delineate the zones of location attractiveness for SMRs and other renewable energy sources. While large and medium-sized cities exhibit optimal location attractiveness, coastal counties in northern Poland emerge as more suitable for renewable energy sources than for SMRs. The study outlines four distinct energy development strategies based on typologies of regions, each tailored to maximize the utility of available resources and minimize environmental impact. The strategies encompass renewable energy utilization, energy efficiency enhancement, energy diversification, and adaptation through innovation. Emphasizing the interplay between renewable energy potential, energy demand, and local conditions, the research suggests the strategic deployment of SMRs as part of an energy mix in areas where renewable energy resources are limited. By leveraging SMRs’ continuous energy production, these reactors can complement intermittent renewables, bolstering energy security.

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Preliminary three-dimensional neutronic analysis of IFBA coated TRISO fuel particles in prismatic-core advanced high temperature reactor

Cited by 16 publications

References 14 publications

Quantitative Analysis Study of Effects of Nuclide Concentration Uncertainties on Biases and Bias Uncertainties in Criticality Calculation Method

Quantitative Analysis Study of Effects of Nuclide Concentration Uncertainties on Biases and Bias Uncertainties in Criticality Calculation Method

An improved optical length research on the physical boundary of particle-dispersed fuel

Small Modular Reactors (SMRs) as a Solution for Renewable Energy Gaps: Spatial Analysis for Polish Strategy

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