Developed high-strength high-ductility 46.7 GPa.% austenitic stainless steel as fuel cladding in fast nuclear reactor

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-04-17 DOI:10.1016/j.nucengdes.2025.114080

Sara E. Saleh , M.K. Elfawakhry , R.M. El Shazly , Heba A. Saudi , S.M. El-Minyawi , M.M. Eissa

{"title":"Developed high-strength high-ductility 46.7 GPa.% austenitic stainless steel as fuel cladding in fast nuclear reactor","authors":"Sara E. Saleh , M.K. Elfawakhry , R.M. El Shazly , Heba A. Saudi , S.M. El-Minyawi , M.M. Eissa","doi":"10.1016/j.nucengdes.2025.114080","DOIUrl":null,"url":null,"abstract":"<div><div>Four samples of austenitic stainless steel were prepared to study the effect of adding titanium, and nickel/chromium modification on the characteristic properties of ordinary austenitic stainless steels, AISI304L and AISI316L that are used in a fuel cladding in fast breeder reactor and the characteristic properties of the developed steels have been compared with the standard alloys. Thermo-calc program FEDAT database was used to predict the phases that can be formed in the different alloys from room temperature to elevated temperature. The constituent phases have been detected by scanning electron microscope attached with EDS and X-ray diffraction. The mechanical properties of investigated stainless-steel alloys were monitored through using uniaxial tensile test, and impact resistance. Corrosion resistance of the studied stainless-steel alloys were investigated in 3.5 % NaCl solution to determine their corrosion rate. The results refer to that the modified austenitic stainless-steel samples with nickel increment at the expense of chromium and micro-alloyed with titanium have preferable mechanical properties in comparison with the standard austenitic stainless-steels AISI316L and AISI304L The yield strength of the developed stainless-steel alloys is enhanced by 21 % and 4 % compared to the standard SS304L and SS316L alloys, respectively. This directly improves the material’s ability to endure extreme conditions, ensuring greater reactor safety, longevity, and performance. The developed SS304LTi showed the best combined high-strength and high-ductility with 46.7 GPa.%. In addition, Furthermore, the corrosion rates of the developed stainless-steel alloys were found to be 58 % and 41 % lower than those of the standard SS304L and SS316L alloys, respectively. This reduction is highly significant, particularly in terms of safety, durability, and the overall efficiency of the reactor.</div><div>To investigate the accommodate of the developed stainless steels in structure of nuclear reactor, four different types of neutron energies were used to determine the macroscopic neutron cross-sections (Σ, cm-1) for the prepared stainless-steel alloys and mean free path was calculated. WinX-com computer program (Version 3.1), and nine experiments of different gamma ray energy lines up to 1.4 MeV were used to determine the mass attenuation coefficients (σ, cm2/g) of gamma rays for the prepared stainless-steel alloys. Good agreement was found between the experimental and calculated values of mass attenuation coefficient. The developed SS304LTi and SS316LTi austenitic stainless steels have lower HVL comparing with the standard SS304L and SS316L, and consequently higher effectiveness of shielding material at the related photon energy. Furthermore, the developed SS304LTi and SS316LTi austenitic stainless steels showed greater values of macroscopic cross-sections and lower values of MFP in all types of neutron energies comparing with the standard SS304L and SS316L steels.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"438 ","pages":"Article 114080"},"PeriodicalIF":1.9000,"publicationDate":"2025-04-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549325002572","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}

引用次数: 0

Abstract

Four samples of austenitic stainless steel were prepared to study the effect of adding titanium, and nickel/chromium modification on the characteristic properties of ordinary austenitic stainless steels, AISI304L and AISI316L that are used in a fuel cladding in fast breeder reactor and the characteristic properties of the developed steels have been compared with the standard alloys. Thermo-calc program FEDAT database was used to predict the phases that can be formed in the different alloys from room temperature to elevated temperature. The constituent phases have been detected by scanning electron microscope attached with EDS and X-ray diffraction. The mechanical properties of investigated stainless-steel alloys were monitored through using uniaxial tensile test, and impact resistance. Corrosion resistance of the studied stainless-steel alloys were investigated in 3.5 % NaCl solution to determine their corrosion rate. The results refer to that the modified austenitic stainless-steel samples with nickel increment at the expense of chromium and micro-alloyed with titanium have preferable mechanical properties in comparison with the standard austenitic stainless-steels AISI316L and AISI304L The yield strength of the developed stainless-steel alloys is enhanced by 21 % and 4 % compared to the standard SS304L and SS316L alloys, respectively. This directly improves the material’s ability to endure extreme conditions, ensuring greater reactor safety, longevity, and performance. The developed SS304LTi showed the best combined high-strength and high-ductility with 46.7 GPa.%. In addition, Furthermore, the corrosion rates of the developed stainless-steel alloys were found to be 58 % and 41 % lower than those of the standard SS304L and SS316L alloys, respectively. This reduction is highly significant, particularly in terms of safety, durability, and the overall efficiency of the reactor.

To investigate the accommodate of the developed stainless steels in structure of nuclear reactor, four different types of neutron energies were used to determine the macroscopic neutron cross-sections (Σ, cm-1) for the prepared stainless-steel alloys and mean free path was calculated. WinX-com computer program (Version 3.1), and nine experiments of different gamma ray energy lines up to 1.4 MeV were used to determine the mass attenuation coefficients (σ, cm2/g) of gamma rays for the prepared stainless-steel alloys. Good agreement was found between the experimental and calculated values of mass attenuation coefficient. The developed SS304LTi and SS316LTi austenitic stainless steels have lower HVL comparing with the standard SS304L and SS316L, and consequently higher effectiveness of shielding material at the related photon energy. Furthermore, the developed SS304LTi and SS316LTi austenitic stainless steels showed greater values of macroscopic cross-sections and lower values of MFP in all types of neutron energies comparing with the standard SS304L and SS316L steels.

查看原文本刊更多论文

开发出高强度高延性46.7 GPa。快堆燃料包壳用奥氏体不锈钢

制备了4个奥氏体不锈钢试样，研究了添加钛和镍铬改性对快中子增殖反应堆燃料包壳用普通奥氏体不锈钢AISI304L和AISI316L特征性能的影响，并与标准合金进行了性能比较。采用热计算程序FEDAT数据库，对不同合金在室温至高温条件下可形成的相进行了预测。用扫描电子显微镜、能谱仪和x射线衍射仪对其组成相进行了检测。通过单轴拉伸试验监测了所研究不锈钢合金的力学性能和抗冲击性能。研究了所研究的不锈钢合金在3.5% NaCl溶液中的耐蚀性，测定了其腐蚀速率。结果表明：以铬为减镍的改性奥氏体不锈钢试样与AISI316L和AISI304L合金相比，具有较好的力学性能，其屈服强度比标准的SS304L和SS316L合金分别提高了21%和4%。这直接提高了材料承受极端条件的能力，确保了更高的反应堆安全性、寿命和性能。开发的SS304LTi具有最佳的高强高塑性结合性能，gpa为46.7 %。此外，所研制的不锈钢合金的腐蚀速率比标准的SS304L和SS316L合金分别降低了58%和41%。这种减少是非常显著的，特别是在安全性、耐久性和反应堆的整体效率方面。为了研究所制备的不锈钢在核反应堆结构中的容纳性，采用四种不同类型的中子能量测定了所制备的不锈钢合金的宏观中子截面（Σ， cm-1），并计算了平均自由程。利用WinX-com 3.1版计算机程序和高达1.4 MeV的9条不同γ射线能量线实验，确定了所制备的不锈钢合金γ射线的质量衰减系数（σ, cm2/g）。质量衰减系数的实验值与计算值吻合较好。研制的SS304LTi和SS316LTi奥氏体不锈钢与标准的SS304L和SS316L相比，具有更低的HVL，因此在相关光子能量下屏蔽材料的效率更高。此外，与标准的SS304L和SS316L钢相比，开发的SS304LTi和SS316LTi奥氏体不锈钢在各种中子能量下的宏观截面值更高，MFP值更低。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.