Unpacking model inadequacy: The quantification of silver release from TRISO fuel by considering empirical and mechanistic approaches

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Somayajulu L.N. Dhulipala , Pierre-Clément A. Simon , Paul A. Demkowicz , Jacob A. Hirschhorn , Stephen R. Novascone
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引用次数: 0

Abstract

Increasing adoption of the proposed tristructural isotropic (TRISO) particle fuel for both advanced and existing reactors makes it critical to assess and address any uncertainties and inadequacies of TRISO fission product release models. Model inadequacy stems from simplifications made to the computational model when compared to the experiments. The modeling and simulation efforts conducted using the BISON fuel performance code, along with the experimental campaigns carried out under the Advanced Gas Reactor Fuel Development and Qualification Program, afford a unique opportunity to conduct a rigorous modeling inadequacy assessment within the Bayesian uncertainty quantification (UQ) framework. This study compares the standard Bayesian framework against the Kennedy-O'Hagan (KOH) framework, which explicitly represents modeling inadequacy, in regard to UQ for TRISO silver release models. For this purpose, both the traditional Arrhenius equation fitted to experimental data and the more advanced lower-length-scale (LLS)-informed model, which considers microstructure information, are independently considered. Applying the inverse UQ process on the AGR-2 and -3/4 datasets revealed modeling inadequacy to be the most dominant source of uncertainty. Experimental noise uncertainty is also significant; however, model parameter uncertainty can be considered negligible. Interestingly, both the Arrhenius equation and the LLS-informed model demonstrated similar levels of modeling inadequacy. For the forward predictive UQ, the KOH framework improved both the accuracy and quality of quantified uncertainties in comparison to the standard Bayesian framework. This is true for both the Arrhenius equation and the LLS-informed model. In comparing these modeling approaches, both demonstrated similar performance at the engineering scale, while the LLS-informed model expectedly outperformed the Arrhenius equation at the mesoscale. These conclusions highlight the importance of explicitly accounting for modeling inadequacy in the UQ process, and reinforce the need for continuous refinement of physics-based models in order to address the modeling inadequacy.
解包模型的不足:量化的银释放从三iso燃料考虑经验和机制的方法
在先进和现有反应堆中越来越多地采用拟议的三结构各向同性(TRISO)颗粒燃料,这使得评估和解决TRISO裂变产物释放模型的任何不确定性和不足之处至关重要。模型的不足源于与实验相比对计算模型的简化。使用BISON燃料性能规范进行的建模和仿真工作,以及在先进气体反应堆燃料开发和鉴定计划下进行的实验活动,为在贝叶斯不确定性量化(UQ)框架内进行严格的建模不足性评估提供了独特的机会。本研究将标准贝叶斯框架与Kennedy-O'Hagan (KOH)框架进行了比较,后者明确表示了关于TRISO银释放模型的UQ的建模不足。为此,分别考虑了适合实验数据的传统Arrhenius方程和考虑微观结构信息的更先进的低长度尺度(LLS)知情模型。将反UQ过程应用于AGR-2和-3/4数据集,发现建模不足是不确定性的最主要来源。实验噪声的不确定性也很显著;然而,模型参数的不确定性可以忽略不计。有趣的是,Arrhenius方程和lls模型都显示出相似程度的建模不足。对于前向预测UQ,与标准贝叶斯框架相比,KOH框架提高了量化不确定性的准确性和质量。这对于Arrhenius方程和lls模型都是正确的。在比较这些建模方法时,两者在工程尺度上都表现出相似的性能,而LLS-informed模型在中尺度上的表现预期优于Arrhenius方程。这些结论强调了在UQ过程中明确说明建模不足的重要性,并强调了为了解决建模不足而不断改进基于物理的模型的必要性。
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来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
期刊介绍: The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.
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