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Gas entrainment allowance level at free surface and gas dynamic behavior of sodium-cooled fast reactor

机译：钠冷快堆自由表面的气体夹带量水平和气体动力学行为

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摘要

In a sodium-cooled fast reactor (SFR), inert gases exist in the primary coolant system either in a state of dissolved gas or free gas bubbles. The sources of the gas bubbles are entrainment and dissolution of the reactor cover gas (argon) at the vessel free surface and emission of the helium gas that is produced as a result of disintegration of B_4C control rod material. The gas in the primary system may cause disturbance in reactivity, nucleation site for boiling, etc. Therefore, it is a key issue from the design and safety viewpoint and the allowance level is necessary regarding the gas entrainment at the free surface and the gas bubble concentration in the primary system. In the present study, a gas entrainment allowance level at the free surface is discussed and rationalized for the Japanese SFR (JSFR) design. The influence of the gas entrainment is evaluated using the void fraction at the core inlet. Design criteria for the acceptable level of the gas entrainment and gas concentration are proposed in consideration of the background level of gasses in the coolant. For the purpose, a plant dynamics code VIBUL has been developed to apply to the JSFR design to evaluate the concentration distribution of the dissolved gas and the free gas bubble in the JSFR system. Using the plant dynamics code for the bubble behavior, the background level of the free gas (void fraction at the core inlet) has been obtained. Assuming that the total void fraction should be kept below 105% of the background level, a preliminary design allowance level of gas entrainment is proposed as the map in terms of the entrainment rate and the entrained bubble radius. Furthermore, the possibility of bubble removal and design requirement of the device is investigated to satisfy the allowance level. It is noted that the background level is already very low in comparison with the induced void reactivity by the void passing the reactor core.
机译：在钠冷快堆（SFR）中，惰性气体以溶解气体或自由气泡的状态存在于主冷却剂系统中。气泡的来源是容器自由表面上反应器盖层气体（氩气）的夹带和溶解，以及由于B_4C控制棒材料的分解而产生的氦气的散发。一次系统中的气体可能会引起反应性的扰动，沸腾的成核部位等。因此，从设计和安全的角度来看，这是一个关键问题，对于自由表面处的气体夹带和气泡，允许水平是必要的集中在主要系统中。在本研究中，针对日本SFR（JSFR）设计，对自由表面的气体夹带允许量进行了讨论和合理化。气体夹带的影响是使用岩心入口处的空隙率来评估的。考虑到冷却剂中气体的背景水平，提出了关于气体夹带和气体浓度的可接受水平的设计标准。为此，已经开发了一种工厂动力学代码VIBUL来应用于JSFR设计，以评估JSFR系统中溶解气体和自由气泡的浓度分布。使用针对气泡行为的工厂动力学代码，可以获得游离气体的背景水平（岩心入口处的空隙分数）。假设总空隙率应保持在背景水平的105％以下，则建议根据夹带率和夹带气泡半径将气体夹带的初步设计允许水平作为映射。此外，研究了气泡去除的可能性和装置的设计要求以满足允许水平。注意，与通过反应堆堆芯的空隙引起的空隙反应性相比，本底水平已经非常低。

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  • 来源
    《Nuclear Engineering and Design》 |2011年第5期|p.1627-1635|共9页
  • 作者

    AkiraYamaguchi41Eisaku Tatsumi; Takashi Takata; Kei Ito; Hiroyuki Ohshima; Hideki Kamide; Jun Sakakibara;

  • 作者单位

    Osaka University, 2-1, Yamada, Suita, Osaka 565-0871, Japan;

    Osaka University, 2-1, Yamada, Suita, Osaka 565-0871, Japan;

    Japan Atomic Energy Agency, 4002, Oarai, Ibaraki 311-1393, Japan;

    Japan Atomic Energy Agency, 4002, Oarai, Ibaraki 311-1393, Japan;

    Japan Atomic Energy Agency, 4002, Oarai, Ibaraki 311-1393, Japan;

    University o/Tsukuba, Tennoudai 1-1-1, Tsukuba, Ibaraki 305-8573, Japan;

  • 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);
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