Monte Carlo simulation of dispersed coated particles in accident tolerant fuel for innovative nuclear reactors

Wu, Yuxuan; Liu, Shichang; Li, Mancang; Xiao, Peng; Wang, Lianjie; Chen, Yixue

doi:10.1002/er.6127

Cited by 12 publications

(3 citation statements)

References 16 publications

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“…Further, the recent geopolitical landscape, exemplified by the 2022 Russian invasion of Ukraine and subsequent EU sanctions, has amplified the European emphasis on energy independence. Significant research efforts are underway to optimize the design of next-generation nuclear reactors, enhancing safety, efficiency, and sustainability [ 29 – 31 ]. This focus, whether on self-reliance, on partnering with reliable allies or on next-generation reactors has made it crucial to measure public attitudes on nuclear energy as means to bolster national energy independence.…”

Section: Literature Reviewmentioning

confidence: 99%

Nuclear energy acceptance in Poland: From societal attitudes to effective policy strategies—Network modeling approach

Smolinski,

Januszewicz,

Pawlowska

et al. 2024

PLoS ONE

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Poland is currently undergoing substantial transformation in its energy sector, and gaining public support is pivotal for the success of its energy policies. We conducted a study with 338 Polish participants to investigate societal attitudes towards various energy sources, including nuclear energy and renewables. Applying a novel network approach, we identified a multitude of factors influencing energy acceptance. Political ideology is the central factor in shaping public acceptance, however we also found that environmental attitudes, risk perception, safety concerns, and economic variables play substantial roles. Considering the long-term commitment associated with nuclear energy and its role in Poland’s energy transformation, our findings provide a foundation for improving energy policy in Poland. Our research underscores the importance of policies that resonate with the diverse values, beliefs, and preferences of the population. While the risk-risk trade-off and technology-focused strategies are effective to a degree, we advocate for a more comprehensive approach. The framing strategy, which tailors messages to distinct societal values, shows particular promise.

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Section: Literature Reviewmentioning

confidence: 99%

Nuclear energy acceptance in Poland: From societal attitudes to effective policy strategies—Network modeling approach

Smolinski,

Januszewicz,

Pawlowska

et al. 2024

PLoS ONE

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“…To solve the problem, many equivalent solutions of neutronics calculation are proposed, such as Reactivity-equivalent Physical Transformation (RPT)method (Lei et al, 2020;Li et al, 2018), the equivalent homogenization method (She et al, 2017) implemented in VSOP (Teuchert et al, 1994) and PANGU (She et al, 2018;She et al, 2021), the volumetric homogenization method (VHM), subgroup method for the resonance treatment, the Sanchez-Pomraning method (Sanchez and Pomraning, 1991;Hébert, 1993) implemented in Dragon and Apollo. These methods often require fine calculations to generate the initial solution, and the fine computational processing is more complex and time-consuming (Wu et al, 2021). Among these methods, the VHM is simpler and faster than others.…”

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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“…17 These assumptions describe some of the properties of the reactor well, including the ratio of dummy and fuel pebbles, but it fails to reveal the random distribution of the pebbles, as well as the stochastic fuel region of the fuel pebble. Wu et al 18 found a novel method to model a dispersed coated particles fuel element, implemented in Monte Carlo code RMC, in which study the burnup calculation of several pebbles was paid attention to, and as far as we know the whole core criticality analysis has not been discussed. Ortensi et al 13 performed the simulation on Serpent and improved the geometry model of the core by using PEBBLES to simulate the idealistic locations of the pebbles with bodycentered cubic (BCC) arrangement.…”

Section: Introductionmentioning

confidence: 99%

Effects of the central graphite column dimension and pebble size on power density distribution in annular core pebble‐bed HTR

Yang

Gui

Huang

et al. 2022

Intl J of Energy Research

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Summary Pebble‐bed HTR utilizes the configuration of randomly distributed graphite and fuel pebbles which contain randomly dispersed TRISO particles, causing the double heterogeneity effect and making simulation get complicated. To establish a high‐fidelity whole core model of the annular core pebble‐bed HTR, this article proposes a two‐step whole core modelling scheme with flexibility. This scheme is verified by comparing the HTR‐10 initial critical benchmark results with the HTR‐10 experiment results. Based on the geometry modelling method and Monte Carlo simulation, this study investigates the effect of the central graphite column dimension and the pebble size upon the nuclear heating power density distribution in annular core pebble‐bed HTR. Results show that the annular core reactor has a more edgy distribution of neutron flux and nuclear heating power density and a higher peak value, compared with the cylindrical configuration core reactor. The annular core reactors with a higher thermal power could realize a higher helium outlet temperature with a precondition that the outlet helium flow is carefully separated and mixed. Accordingly, a higher thermoelectric conversion efficiency could be achieved. Reactors filled with smaller pebbles reach the criticality more quickly. However, the radius of the pebbles in the range from 2.5 to 3.5 cm does less effect than the size of the central graphite column does to the neutron flux and nuclear heating power density distribution. The running‐in phase of the annular configuration core reactor is investigated in the last section. The heating power density gradually flattens as the initial core pebbles fall and new fuel pebbles are loaded into the cavity. In this running‐in phase, we adopt a one‐to‐one mapping technique that sets the temperature of pebbles to their real value, varying from their locations. This enables us to do further work of the neutronics/thermal‐hydraulics analysis and the dynamic simulation which fit the realistic engineering practice, and to explore the fuel management scheme of the annular core high‐temperature gas‐cooled pebble‐bed reactor.

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Monte Carlo simulation of dispersed coated particles in accident tolerant fuel for innovative nuclear reactors

Cited by 12 publications

References 16 publications

Nuclear energy acceptance in Poland: From societal attitudes to effective policy strategies—Network modeling approach

Nuclear energy acceptance in Poland: From societal attitudes to effective policy strategies—Network modeling approach

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

Effects of the central graphite column dimension and pebble size on power density distribution in annular core pebble‐bed HTR

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