Development of FEMAXI-ATF for fuel performance modeling of SiC cladded fuel involving PCMI

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Yoshihiro Kubo, Akifumi Yamaji
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引用次数: 0

Abstract

The SiC cladded fuel is being developed as a candidate for the accident tolerant fuel of light water reactors, in which the cladding wall consists of the inner SiC/SiC layer and the outer monolithic (mSiC) layer. The FEMAXI-ATF fuel performance modeling code is being developed based on the experience of FEMAXI-7 with the focus on evaluation of the pellet-cladding mechanical interaction (PCMI). In the preceding study, the capability of FEMAXI-ATF to show the PCMI failure limit of the SiC cladded fuel was successfully demonstrated by modeling the SiC/SiC layer with a continuum finite calculation element and reducing Young's modulus of the failed element to practically zero, so that the stress on the cladding wall is redistributed among the remaining cladding wall elements. In this study, FEMAXI-ATF has been further developed to consider pseudo-ductility of SiC/SiC and improvement to the temperature dependent SiC swelling model. The new FEMAXI-ATF was applied in the BWR normal operation conditions to show a possible scenario. That is, the SiC cladded fuel may experience partial failure of the SiC/SiC layer during the reactor shutdown depending on the swelling characteristics of SiC. Consequently, PCMI may induce large mechanical load on the mSiC layer in the subsequent operation.
基于PCMI的SiC包覆燃料性能建模femaxis - atf的开发
SiC包覆燃料是一种由内SiC/SiC层和外单片(mSiC)层组成的轻水反应堆耐事故燃料候选材料。femaxis - atf燃料性能建模代码正在根据femaxis -7的经验开发,重点是评估颗粒包层机械相互作用(PCMI)。在之前的研究中,femaxis - atf通过连续有限计算单元对SiC/SiC层进行建模,并将失效单元的杨氏模量降至几乎为零,从而将包层壁上的应力重新分配到剩余的包层壁上,成功地证明了femaxis - atf显示SiC包层燃料PCMI失效极限的能力。在本研究中,femaxis - atf进一步发展,考虑了SiC/SiC的伪延性,并改进了温度相关的SiC膨胀模型。将新型femaxis - atf应用于沸水堆正常运行条件下,以展示可能的场景。也就是说,根据SiC的膨胀特性,在反应堆关闭期间,SiC包覆燃料可能会经历SiC/SiC层的部分失效。因此,PCMI可能会在随后的操作中对mSiC层产生较大的机械负载。
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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