球床高温反应堆可裂变同位素定量的多变量分析

IF 3.2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Progress in Nuclear Energy Pub Date : 2025-02-01 Epub Date: 2024-12-24 DOI:10.1016/j.pnucene.2024.105589
Hongjian Zhang, Qing Zhu, Haiyan Xiao, Liguo Zhang, Tao Ma
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引用次数: 0

摘要

球床高温气冷堆在连续换料状态下运行,使得堆芯内单个燃料球的轨迹不确定。这种固有的跟踪能力的缺乏导致燃料球的燃耗历史模糊不清。因此,传统的以初始燃料成分为基础,通过燃耗计算来推算球床反应堆核燃料中核素存量的方法是不可行的。目前,虽然与高温反应堆-球床模块集成的在线燃耗测量系统允许采集伽马射线能谱,使某些核素活动的测量成为可能,但可裂变同位素的直接无损测量仍然难以捉摸。这一限制对核材料核算领域提出了重大挑战,需要创新方法来准确评估库存。本研究提出了一种提高球床堆中裂变同位素和Zr-95预测精度的综合方法,包括三个研究方面。首先,采用离散元法(DEM)模型对球床堆芯进行了数值模拟。通过选择合适的接触模型和调整模型参数,根据三维卵石流实验数据对模型进行校准,以确保流动弥散、径向流速比等关键指标的一致性。随后,根据燃料球在堆芯内的轨迹,构建了燃料球的辐照历史。然后将这些数据与核素库存计算软件集成,以模拟燃料球的燃耗信息。最后,该研究采用多元分析技术,包括主成分分析(PCA)、脊回归和随机森林模型,从在线可测量的放射性核素的活性中预测可裂变同位素和Zr-95。我们的方法的预测准确性是通过将由模拟数据集训练的多元线性模型产生的结果与来自实验数据的结果相关联来评估的。本文建立了球床高温堆裂变同位素的计算方法,提高了核材料核算的精度,Zr-95的预测误差仅为4.9%,是目前能得到的最准确的实验数据。这表明在线核素含量包含有价值的信息,值得进一步探索,并验证了多元分析方法在核材料计算中的适用性。
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Multivariate analysis quantifying amount of fissile isotopes for pebble-bed high temperature reactors
Pebble-bed high-temperature gas-cooled reactors operate under a continuous refueling regime, rendering the trajectory of individual fuel spheres within the reactor core indeterminate. This inherent lack of tracking capability results in an obscured burnup history for the fuel spheres. Consequently, the conventional approach of deducing the nuclide inventory in the nuclear fuel of pebble-bed reactors through burnup calculations, predicated on initial fuel composition, is infeasible. Presently, while the online Burnup Measurement System integrated with High Temperature Reactor-Pebble bed Modules allows for the acquisition of gamma-ray spectra, enabling the measurement of certain nuclide activities, the direct non-destructive measurement of fissile isotopes remains elusive. This limitation poses a significant challenge to the field of nuclear material accounting, necessitating innovative methodologies for accurate inventory assessment.
This study presents a comprehensive approach to enhance the predictive accuracy of fissile isotopes and Zr-95 in pebble-bed reactors, encompassing three research facets. Initially, the Discrete Element Method (DEM) model is employed to simulate the core of a pebble-bed reactor. The model is calibrated against three-dimensional pebble flow experimental data by selecting an appropriate contact model and tuning model parameters to ensure consistency in flow dispersion, radial velocity ratio, and other key metrics. Subsequently, irradiation histories for the fuel spheres are constructed based on their trajectories within the reactor core. This data is then integrated with a nuclide inventory calculation software to simulate burnup information for the fuel spheres. Finally, the study employs multivariate analysis techniques, including Principal Component Analysis (PCA), ridge regression, and the random forest model, to predict fissile isotopes and Zr-95 from activity of online-measurable radionuclides. The predictive accuracy of our approach is appraised by correlating the outcomes yielded by a multivariate linear model, trained with simulated datasets, against those derived from experimental data.
This paper establishes a computational method for fissile isotopes in pebble-bed high-temperature reactors, enhancing the accuracy of nuclear material accounting, with a prediction error of only 4.9% for Zr-95, which is the most accurate experimental data that can be obtained. It demonstrates that online nuclide content contains valuable information worth further exploration and validates the applicability of multivariate analysis methods in nuclear material calculations.
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来源期刊
Progress in Nuclear Energy
Progress in Nuclear Energy 工程技术-核科学技术
CiteScore
5.30
自引率
14.80%
发文量
331
审稿时长
3.5 months
期刊介绍: Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
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