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Advanced method for neutronic simulation of control rods in sodium fast reactors: Numerical and experimental validation

机译:钠快堆中控制棒的中子模拟的先进方法:数值和实验验证

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摘要

High accuracy neutronic simulations are required for the development of Generation-IV sodium cooled fast reactors (SFR). This paper therefore focuses on the development and validation of an improved calculation method in APOLLO3 (R) deterministic code to predict the reactivity control system in SFR.This method relies on the "lattice-core" paradigm and the generation of few group effective cross-sections. Those are computed over small lattice geometries with detailed descriptions of structures but no heterogeneity correction method. Two models are considered at the core level: the first one relies on homogeneous descriptions for all assemblies (fuel, control rods, reflector, diluent, etc.), whereas the second one takes into account the heterogeneity of absorber pins (semi-heterogeneous description).In order to assess the robustness of calculation methods, a validation work is achieved for three distinct SFR cores. A numerical validation is first performed for the SFR-3600-MOX core taken from the international WPRS benchmark. Then an experimental validation work is conducted for the control rods measurements from SUPERPHENIX start-up experiments. The last case of application is the ASTRID CFV core. At the cross-sections generation stage, the results show a good coherence with reference Monte Carlo calculations for both spatial and energy distributions. At the core level, it is shown that the homogeneous description of the control rods induces an overestimation of the reactivity worth while the semi-heterogeneous model significantly improves the results. (C) 2019 Elsevier Ltd. All rights reserved.
机译:IV代钠冷却快堆(SFR)的开发需要高精度的中子模拟。因此,本文着眼于APOLLO3(R)确定性代码中改进的计算方法的开发和验证,以预测SFR中的反应性控制系统。该方法依赖于“晶格核心”范式和少数有效组的生成交叉区域。这些是在具有详细结构描述但没有异质性校正方法的小晶格几何结构上计算的。在核心级别考虑了两个模型:第一个模型依赖于所有组件(燃料,控制杆,反射器,稀释剂等)的统一描述,而第二个模型则考虑了吸收销的异质性(半异构描述) )。为了评估计算方法的稳健性,针对三个不同的SFR内核进行了验证工作。首先根据国际WPRS基准对SFR-3600-MOX内核进行数值验证。然后对SUPERPHENIX启动实验进行的控制棒测量进行实验验证工作。最后一种应用是ASTRID CFV内核。在横截面生成阶段,结果与参考蒙特卡洛计算在空间和能量分布方面都显示出良好的一致性。在核心水平上,表明控制棒的均质描述导致对反应性价值的高估,而半均质模型则显着改善了结果。 (C)2019 Elsevier Ltd.保留所有权利。

著录项

  • 来源
    《Annals of nuclear energy》 |2019年第7期|90-100|共11页
  • 作者单位

    CEA, Alternat Energies & Atom Energy Commiss, DEN, SPRC, F-13108 St Paul Les Durance, France;

    CEA, Alternat Energies & Atom Energy Commiss, DEN, SPRC, F-13108 St Paul Les Durance, France;

    CEA, Alternat Energies & Atom Energy Commiss, DEN, SPRC, F-13108 St Paul Les Durance, France;

    CEA, Alternat Energies & Atom Energy Commiss, DEN, SPRC, F-13108 St Paul Les Durance, France;

    CEA, Alternat Energies & Atom Energy Commiss, DEN, SPRC, F-13108 St Paul Les Durance, France;

    CEA, Alternat Energies & Atom Energy Commiss, DEN, SPRC, F-13108 St Paul Les Durance, France;

    CEA, Alternat Energies & Atom Energy Commiss, DEN, SPRC, F-13108 St Paul Les Durance, France;

  • 收录信息
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Neutronics; Control rods; Fast reactor; APOLLO3 (R);

    机译:中子学;控制杆;快速反应堆;APOLLO3(R);

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