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1.
The electric charges to enhance the localized in-pile corrosion are estimated quantitatively by a model analogous to an electric circuit. The model is more detailed than that reported in the previous papers. It is applied to the cases of a fuel cladding near platinum in the Halden experiments and a fuel channel near a control blade. As a result, respecting the electric charges to enhance the localized oxidation, both cases investigated in this work are explained quantitatively by the total amount of electric current, from all the localized electrochemical cells between the surface of zirconium oxide adjacent to and facing to bare and grounded metals such as platinum or stainless steel and its neighboring parts, introduced by the “β-induced electric fields” on zirconium oxide.

The electric potential of the electrochemical cell concerned decreases in the course of oxidation, and therefore, the retardation of oxidation during the growth of the oxide film can be explained by the fact that the electric current by the above electrochemical cell becomes insufficient to enhance the localized oxidation.  相似文献   

2.
非能动堆芯冷却系统LOCA下冷却能力分析   总被引:1,自引:0,他引:1  
本文基于机理性分析程序建立了包括反应堆一回路冷却剂系统、专设安全设施及相关二次侧管道系统的先进压水堆分析模型,对典型的小破口失水事故和大破口失水事故开展了全面分析。针对不同破口尺寸、破口位置的失水事故,分析了非能动堆芯冷却系统(PXS)中非能动余热排出系统(PRHRS)、堆芯补水箱(CMT)、安注箱(ACC)、自动卸压系统(ADS)和安全壳内置换料水箱(IRWST)等关键系统的堆芯注水能力和冷却效果。研究表明,虽然破口尺寸、破口位置会影响事故进程发展,但所有事故过程中燃料包壳表面峰值温度不超过1 477 K,且反应堆堆芯处于有效淹没状态。PXS能有效排出堆芯衰变热,将反应堆引导到安全停堆状态,防止事故向严重事故发展。  相似文献   

3.
Heat transfer coefficients of steam condensation on the containment vessel wall at a LOCA are studied. As to the steady state heat transfer coefficients, though Sagawa's data are a little smaller than Uchida's data, they are very close to the analytical solutions by Mori-Hijikata. Transient heat transfer coefficients are represented by the steady state heat transfer coefficients multiplied by a factor. The factor expresses the agitation effect weakening with time during blowdown. Values of parameters in the factor are determined so as the heat transfer coefficients to fit Sagawa's data. These heat transfer coefficients are applied to the analyses of the experiment with the simulation apparatus of an integrated type marine water reactor. Values of the parameters are also determined so that the temperature transients on the containment vessel wall by analyses fit them of experiment. The differences of the values of parameters by the analyses and by Sagawa's data are discussed.  相似文献   

4.
In this paper, an attempt has been made to systematically organize the research investigations conducted on clad tube failure, so far. Before presenting the review on the clad failure studies, an introduction to different clad materials has been added, in which the effect of alloying elements on the material properties have been presented. The literature on clad failure has been broadly categorized under the headings LOCA and RIA. The failure mechanisms like creep, corrosion and pellet-clad interaction have been discussed in details. Each subsection of the review has been provided with summary table, in which the studies are arranged in the chronological order. A small section on acceptance criteria for ECCS has also been included. The last section of the review has been dedicated to the core-degradation phenomena.  相似文献   

5.
The paper presents variations of a certain passive safety containment for a near future BWR. It is tentatively named Mark S containment in the paper. It uses the operating dome as the upper secondary containment vessel (USCV) to where the pressure of the primary containment vessel (PCV) can be released through the upper vent pipes. One of the merits of the Mark S containment is very low peak pressure at severe accidents without venting the containment atmosphere to the environment. Another merit is the capability to submerge the PCV and the reactor pressure vessel (RPV) above the core level by flooding water from the gravity-driven cooling system (GDCS) pool and the upper pool. The third merit is robustness against external events such as a large commercial airplane crash owing to the reinforced concrete USCV. The Mark S containment is applicable to a large reactor that generates 1830 MW electric power. The paper presents several examples of BWRs that use the Mark S containment. In those examples active safety systems and passive safety systems function independently and constitute in-depth hybrid safety (IDHS). The concept of the IDHS is also presented in the paper.  相似文献   

6.
The paper presents two types of a passive safety containment for a near future BWR. They are named Mark S and Mark X containment. One of their common merits is very low peak pressure at severe accidents without venting the containment atmosphere to the environment. The PCV pressure can be moderated within the design pressure. Another merit is the capability to submerge the PCV and the RPV above the core level. The third merit is robustness against external events such as a large commercial airplane crash. Both the containments have a passive cooling core catcher that has radial cooling channels. The Mark S containment is made of reinforced concrete and applicable to a large power BWR up to 1830 MWe. The Mark X containment has the steel secondary containment and can be cooled by natural circulation of outside air. It can accommodate a medium power BWR up to 1380 MWe. In both cases the plants have active and passive safety systems constituting in-depth hybrid safety (IDHS). The IDHS provides not only hardware diversity between active and passive safety systems but also more importantly diversity of the ultimate heat sinks between the atmosphere and the sea water. Although the plant concept discussed in the paper uses well-established technology, plant performance including economy is innovatively and evolutionally improved. Nothing is new in the hardware but everything is new in the performance.  相似文献   

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