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Molten salt related extensions of the SIMMER-Ⅲ code and its application for a burner reactor

机译:SIMMER-Ⅲ代码与熔盐有关的扩展及其在燃烧器反应堆中的应用

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摘要

Molten salt reactors (MSRs) can be used as effective burners of plutonium (Pu) and minor actinides (MAs) from light water reactor (LWR) spent fuel. In this paper a study was made to examine the thermal hydraulic behaviour of the conceptual design of the molten salt advanced reactor transmuter (MOSART) [Ignatiev, V., Feynberg, O., Myasnikov, A., Zakirov, R., 2003a. Neutronic properties and possible fuel cycle of a molten salt transmuter. Proceedings of the 2003 ANS/ENS International Winter Meeting (GLOBAL 2003), Hyatt Regency, New Orleans, LA, USA 16-20 November 2003]. The molten salt fuel is a ternary NaF-LiF-BeF_2 system fuelled with ca. 1 mol% typical compositions of transuranium-trifluorides (PuF_3, etc.) from light water reactor spent fuel. The MOSART reactor core does not contain graphite structure elements to guide the flow, so the neutron spectrum is rather hard in order to improve the burning performance. Without those structure elements in the core, the molten salt in core flows freely and the flow pattern could be potentially complicated and may affect significantly the fuel temperature distribution in the core. Therefore, some optimizations of the salt flow pattern may be needed. Here, the main attention has been paid to the fluid dynamic simulations of the MOSART core with the code SIMMER-Ⅲ [Kondo, Sa., Morita, K., Tobita, Y, Shirakawa, K., 1992. SIMMER-Ⅲ: an advanced computer program for LMFBR severe accident analysis. Proceedings of the ANP' 92, Tokyo, Japan; Kondo, Sa., Tobita, Y., Morita, K., Brear, D.J., Kamiyama, K., Yamano, H., Fujita, S., Maschek, W, Fischer, E.A., Kiefhaber, E., Buckel, G., Hesselschwerdt, E., Flad, M., Costa, P., Pigny, S., 1999. Current status and validation of the SIMMER-Ⅲ LMFR safety analysis code. Proceedings of the ICONE-7, Tokyo, Japan], which was originally developed for the safety assessment of sodium-cooled fast reactors and recently extended by the authors for the thermo-hydraulic and neutronic models so as to describe the molten salt reactors. For the adaptation to molten salt reactor, a complete equation of state (EOS) for this liquid fuel had to be developed and implemented into the SIMMER-Ⅲ code. Through those simulations it was concluded that the thermal hydraulic behaviour appeared to be very important in molten salt reactors concerning design, operation and safety. A flow distribution plate design was found effective to optimize the flow pattern in the core region. Further investigations are under way to obtain optimal flow fields without exceeding design limits.
机译:熔融盐反应堆(MSR)可用作as(Pu)和轻水反应堆(LWR)乏燃料中次要act系元素(MAs)的有效燃烧器。在本文中,进行了一项研究以检查熔融盐高级反应堆变换器(MOSART)概念设计的热工水力性能[Ignatiev,V.,Feynberg,O.,Myasnikov,A.,Zakirov,R.,2003a。熔融盐变换器的中子学性质和可能的燃料循环。 2003年ANS / ENS国际冬季会议(2003年全球会议)会议记录,凯悦丽晶酒店,美国路易斯安那州新奥尔良[2003年11月16日至20日]。熔融盐燃料是一种三元NaF-LiF-BeF_2系统,其燃料约为。来自轻水反应堆乏燃料的三氟化铀(PuF_3等)的典型成分为1 mol%。 MOSART反应堆堆芯不包含引导流动的石墨结构元素,因此中子光谱相当坚硬,无法改善燃烧性能。在堆芯中没有这些结构元素的情况下,堆芯中的熔融盐会自由流动,流型可能会变得复杂,并且可能会严重影响堆芯中的燃料温度分布。因此,可能需要对盐流模式进行一些优化。在这里,主要关注的是代码为SIMMER-Ⅲ的MOSART核的流体动力学模拟[Kondo,Sa.,Morita,K.,Tobita,Y,Shirakawa,K.,1992.SIMMER-Ⅲ:用于LMFBR严重事故分析的高级计算机程序。 ANP'92会议记录,日本东京; Kondo,Sa.,Tobita,Y.,Morita,K.,Brear,DJ,Kamiyama,K.,Yamano,H.,Fujita,S.,Maschek,W,Fischer,EA,Kiefhaber,E.,Buckel,G 。,Hesselschwerdt,E.,Flad,M.,Costa,P.,Pigny,S.,1999。SIMMER-ⅢLMFR安全分析代码的现状和验证。 [ICONE-7,日本东京的会刊],最初是为钠冷快堆的安全性评估而开发的,最近作者扩展了热工水力和中子学模型,以描述熔融盐反应堆。为了适应熔融盐反应堆,必须开发这种液体燃料的完整状态方程(EOS)并将其实施到SIMMER-Ⅲ代码中。通过这些模拟得出结论,热熔行为在熔融盐反应堆中在设计,运行和安全方面似乎非常重要。发现流量分配板设计可有效优化核心区域的流动模式。正在进行进一步的研究,以获得不超出设计限制的最佳流场。

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  • 来源
    《Nuclear Engineering and Design》 |2006年第16期|p.1580-1588|共9页
  • 作者单位

    Forschungszentrum Karlsruhe, Institute for Nuclear and Energy Technologies, Postfach 3640, D-76021 Karlsruhe, Germany;

  • 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 原子能技术;
  • 关键词

  • 入库时间 2022-08-18 00:46:55

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