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An earthquake transient method for pebble-bed reactors and a fuel temperature model for TRISO fueled reactors.

机译:卵石床反应堆的地震瞬态方法和TRISO燃料堆的燃料温度模型。

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摘要

This investigation is divided into two general topics: (1) a new method for analyzing the safe shutdown earthquake event in a pebble bed reactor core, and (2) the development of an explicit tristructural-isotropic fuel model for high temperature reactors. The safe shutdown earthquake event is one of the design basis accidents for the pebble bed reactor. The new method captures the dynamic geometric compaction of the pebble bed core. The neutronic and thermal-fluids grids are dynamically re-meshed to simulate the re-arrangement of the pebbles in the reactor during the earthquake. Results are shown for the PBMR-400 assuming it is subjected to the Idaho National Laboratory's design basis earthquake. The study concludes that the PBMR-400 can safely withstand the reactivity insertions induced by the slumping of the core and the resulting relative withdrawal of the control rods. This characteristic stems from the large negative Doppler feedback of the fuel. This Doppler feedback mechanism is a major contributor to the passive safety of gas-cooled, graphite-moderated, high-temperature reactors that use fuel based on TRISO particles. The correct prediction of the magnitude and time-dependence of this feedback effect is essential to the conduct of safety analyses for these reactors. An explicit TRISO fuel temperature model named THETRIS has been developed in this work and incorporated in the CYNOD-THERMIX-KONVEK suite of coupled codes. The new model yields similar results to those obtained with more complex methods, requiring multi-TRISO calculations within one control volume. The performance of the code during fast and moderately-slow transients is verified. These analyses show how explicit TRISO models improve the predictions of the fuel temperature, and consequently, of the power escalation. In addition, a brief study of the potential effects on the transient behavior of high-temperature reactors due to the presence of a gap inside the TRISO particles is included. Although the formation of a gap occurs under special conditions, its consequences on the dynamic behavior of the reactor can cause unexpected responses during fast transients, but still the reactor shuts down due to the strong temperature feedback effects.
机译:这项研究分为两个一般主题:(1)一种用于分析卵石床反应堆堆芯安全关闭地震事件的新方法,以及(2)开发用于高温反应堆的显式三向同性燃料模型。安全停机地震事件是卵石床反应堆的设计基准事故之一。新方法捕获了卵石床芯的动态几何压实。动态重塑中子和热流体网格,以模拟地震期间反应堆中卵石的重新排列。显示了PBMR-400的结果,假设它受到了爱达荷州国家实验室的设计基准地震的影响。研究得出的结论是,PBMR-400可以安全地承受由芯塌陷和控制杆相对抽出引起的反应性插入。该特征源自燃料的大负多普勒反馈。这种多普勒反馈机制是使用基于TRISO颗粒的燃料的气冷式石墨调节高温反应堆的被动安全性的主要贡献者。对于这些反应堆进行安全分析,正确预测此反馈效应的大小和时间相关性至关重要。在这项工作中开发了一个名为THETRIS的显式TRISO燃油温度模型,并将其纳入CYNOD-THERMIX-KONVEK耦合代码套件中。新模型产生的结果与采用更复杂方法获得的结果相似,需要在一个控制体积内进行多次TRISO计算。验证了快速和中等慢速瞬态期间的代码性能。这些分析表明,显式的TRISO模型如何改善燃料温度的预测,进而改善功率提升的预测。此外,还简要介绍了由于TRISO颗粒内部存在间隙而对高温反应器的瞬态行为产生的潜在影响。尽管间隙的形成是在特殊条件下发生的,但其对反应堆动态行为的影响会在快速瞬变期间引起意外响应,但由于强烈的温度反馈效应,反应堆仍会关闭。

著录项

  • 作者

    Ortensi, Javier.;

  • 作者单位

    Idaho State University.;

  • 授予单位 Idaho State University.;
  • 学科 Engineering Nuclear.
  • 学位 Ph.D.
  • 年度 2009
  • 页码 117 p.
  • 总页数 117
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 宗教史、宗教地理;
  • 关键词

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