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Modeling the performance of TRISO-based fully ceramic matrix (FCM) fuel in an LWR environment using BISON

机译:使用BISON对LWR环境中基于TRISO的全陶瓷基体(FCM)燃料的性能进行建模

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摘要

Fully ceramic microencapsulated (FCM) fuel is a proposed fuel type for improved accident performance in LWRs (Light Water Reactors) that involves TRISO (TRistructural-ISOtropic) particles embedded in a nano-powder sintered silicon carbide (SiC) matrix. The TRISO particles contain a spherical fuel kernel ranging from 500 to 800 mu m in diameter. The kernel and buffer layer are then coated with three layers, each of which is 30-40 mu m thick, composed of dense inner pyrolytic carbon (IPyC), chemically vapor deposited silicon carbide (SiC) layer, and an outer pyrolytic carbon (OPyC) layer. These TRISO particles are then embedded in a fully dense sintered SiC matrix with an expected particle packing fraction of about 35-40% by volume. As is the case for gas reactor applications, the release of radioactivity into the coolant is dependent on the integrity of the silicon carbide layer of the TRISO particles, in addition to the SiC matrix. In this work, we report on fuel performance modeling of TRISO-bearing FCM fuel using the BISON code to simulate the thermo-mechanical behavior of this fuel in a prototypic LWR environment. This paper considers the effects of embedding a TRISO particle in the SiC pellet matrix and includes a discussion of the irradiation-induced dimensional change in the pyrolytic carbon (PyC) layers of the TRISO particle. Additionally, methods were developed to simulate a FCM pellet containing a large number of discrete and independent particles. Future work will report on developing an interface debonding model, a fracture model, and a radionuclide transport model.
机译:完全陶瓷微囊化(FCM)燃料是一种建议的燃料类型,用于改善轻水堆(LWR)的事故性能,该轻水堆涉及嵌入纳米粉末烧结碳化硅(SiC)基质中的TRISO(TRistructural-ISOtropic)颗粒。 TRISO颗粒包含直径为500至800微米的球形燃料核。然后在内核和缓冲层上覆盖三层,每层厚度为30-40微米,由致密的内部热解碳(IPyC),化学气相沉积的碳化硅(SiC)层和外部热解碳(OPyC)组成)层。然后,将这些TRISO颗粒嵌入到完全致密的SiC烧结烧结基体中,其预期的颗粒堆积率约为35-40%(体积)。与气体反应器的应用一样,除SiC基质外,向冷却剂中的放射性释放还取决于TRISO颗粒的碳化硅层的完整性。在这项工作中,我们使用BISON代码报告了含TRISO的FCM燃料的燃料性能建模,以模拟该燃料在原型LWR环境中的热机械行为。本文考虑了将TRISO颗粒嵌入SiC颗粒基体的效果,并讨论了TRISO颗粒的热解碳(PyC)层中辐照引起的尺寸变化。另外,开发了模拟包含大量离散和独立颗粒的FCM颗粒的方法。未来的工作将报告开发界面脱粘模型,断裂模型和放射性核素传输模型。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2018年第8期|116-127|共12页
  • 作者单位

    Univ Tennessee, Dept Nucl Engn, Knoxville, TN 37996 USA;

    Oak Ridge Natl Lab, Oak Ridge, TN USA;

    Oak Ridge Natl Lab, Oak Ridge, TN USA;

    SUNY Stony Brook, Stony Brook, NY 11794 USA;

    Univ Tennessee, Dept Nucl Engn, Knoxville, TN 37996 USA;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    FCM; TRISO; BISON; Finite element; Fuel performance;

    机译:FCM;TRISO;BISON;有限元;燃油性能;
  • 入库时间 2022-08-18 00:40:43

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