Pre-conceptual design of prestressed concrete containment for a GFR nuclear reactor

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-09-04 DOI:10.1016/j.nucengdes.2025.114425

Petr Bílý, Jakub Holan, Roman Kubát

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引用次数: 0

Abstract

The paper presents the process of a pre-conceptual design, analysis and optimization of a prestressed concrete containment vessel (PCCV) for a new type of gas-cooled fast reactor (GFR). The feasibility of the PCCV concept has been confirmed by a preliminary study presented in a previous paper. This paper builds on the prior results and presents an advanced analysis of the PCCV conducted using a global 3D non-linear coupled thermomechanical finite element model. The model is presented together with the results, revealing problems regarding unacceptable cracks or excessive compressive stresses in atypical areas of the structure (the gusset, the peripheral part of the dome, the ring beam, and the equipment hatch area). In the main part of the paper, various approaches to the modification of these regions are explored (e.g. modifications of geometry, prestress or steel reinforcement of the structure). The considerations that lead to the selection of the most beneficial modifications are explained in detail. The final version of the pre-conceptual design meets all of the defined criteria for the behaviour of the PCCV in the operation stage and during loss of coolant accident (LOCA). The main contributions of the paper are that it: (a) presents the process of modelling, analysis, and optimisation of a PCCV, (b) explores possible approaches to the modification of the atypical parts of a PCCV, (c) provides solutions for various design problems, and (d) presents and verifies a suitable design of a PCCV for a new type of GFR.

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GFR核反应堆预应力混凝土安全壳的概念前设计

本文介绍了一种新型气冷快堆（GFR）的预应力混凝土安全壳（PCCV）的概念前设计、分析和优化过程。PCCV概念的可行性已在先前的论文中提出的初步研究中得到证实。本文在前人研究成果的基础上，采用全局三维非线性耦合热-力学有限元模型对PCCV进行了深入分析。该模型与结果一起呈现，揭示了结构的非典型区域（扣板，圆顶的外围部分，环梁和设备舱口区域）中不可接受的裂缝或过大的压应力问题。在论文的主要部分，探讨了对这些区域进行修改的各种方法（例如几何形状，预应力或结构钢筋的修改）。详细解释了导致选择最有益的修改的考虑因素。概念前设计的最终版本符合PCCV在运行阶段和冷却剂损失事故（LOCA）期间行为的所有定义标准。本文的主要贡献在于：(a)介绍了PCCV的建模、分析和优化过程，(b)探索了PCCV非典型部分修改的可能方法，(c)提供了各种设计问题的解决方案，(d)提出并验证了适用于新型GFR的PCCV设计。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.