A method for design a linear heat rate ramp limit curve for thermal reactor fuel rods

IF 0.4 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY Atomic Energy Pub Date : 2024-09-30 DOI:10.1007/s10512-024-01129-0
A. V. Krupkin, V. I. Kuznetsov, K. V. Loktaev, V. V. Novikov
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Abstract

An increase in power during transient operating modes of reactors can lead to the depressurization of fuel rods due to the stress corrosion cracking mechanism. Expansion of fuel pellets due to increasing power induces tensile stresses in the cladding, which can initiate the formation and growth of corrosion cracks in the presence of aggressive fission products. Therefore, the plotted limit curve is primarily aimed at preventing circumferential stresses in the cladding from exceeding a certain maximum value during abrupt changes in power. The present article describes a system for performing multivariate statistical calculations of a single power increase to plot an envelope curve for the permissible area of fuel rod operation. The system uses the START-3A code to perform fuel rod calculations, which includes the ability to vary model and design parameters. The methodology for the calculated limit curve for a rapid increase in the power of a VVER-1200 reactor is presented with examples.

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设计热核反应堆燃料棒线性热率斜坡限制曲线的方法
在反应堆的瞬态运行模式下,功率的增加会导致燃料棒因应力腐蚀开裂机制而减压。功率增加导致燃料芯块膨胀,从而在包层中产生拉伸应力,在存在侵蚀性裂变产物的情况下,会引发腐蚀裂纹的形成和增长。因此,绘制极限曲线的主要目的是防止在功率突然变化时包层中的圆周应力超过某个最大值。本文介绍了一种对单次功率增加进行多元统计计算的系统,用于绘制燃料棒运行允许区域的包络曲线。该系统使用 START-3A 代码进行燃料棒计算,包括改变模型和设计参数的功能。通过实例介绍了计算 VVER-1200 反应堆功率快速增长极限曲线的方法。
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来源期刊
Atomic Energy
Atomic Energy 工程技术-核科学技术
CiteScore
1.00
自引率
20.00%
发文量
100
审稿时长
4-8 weeks
期刊介绍: Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.
期刊最新文献
Development of a method for measuring the effective fraction of delayed neutrons using a 240Pu spontaneous fission source A method for design a linear heat rate ramp limit curve for thermal reactor fuel rods On the 60th anniversary of the first aperiodic pulsed nuclear reactor in Russia Feasibility study for industrial conditioning of spent ion-exchange resins by impregnation with a polymer binder Technical and economic aspects of a nuclear power engineering plant for hydrogen production
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