رفتار نفوذ دوتریوم از فولاد ضد زنگ 430
ترجمه نشده

رفتار نفوذ دوتریوم از فولاد ضد زنگ 430

عنوان فارسی مقاله: اثر لایه های اکسیدی طبیعی بر رفتار نفوذ دوتریوم از فولاد ضد زنگ 430
عنوان انگلیسی مقاله: Effect of natural oxide film on the deuterium permeation behavior of 430 stainless steel
مجله/کنفرانس: مهندسی فیوژن و طراحی - Fusion Engineering And Design
رشته های تحصیلی مرتبط: شیمی، مهندسی مواد
گرایش های تحصیلی مرتبط: متالورژی، شناسایی و انتخاب مواد مهندسی، خوردگی و پوشش و سطح مهندسی، شیمی کاربردی، خوردگی و حفاظت از مواد
کلمات کلیدی فارسی: نفوذ دوتریوم، لایه اکسیدی، فولاد ضد زنگ 316L، فولاد ضد زنگ 430
کلمات کلیدی انگلیسی: Deuterium permeation، Oxide film، 316L stainless steel، 430 stainless steel
نوع نگارش مقاله: مقاله پژوهشی (Research Article)
نمایه: Scopus - Master Journals List - JCR
شناسه دیجیتال (DOI): https://doi.org/10.1016/j.fusengdes.2020.111469
دانشگاه: China Institute of Atomic Energy, Beijing, 102413, China
صفحات مقاله انگلیسی: 5
ناشر: الزویر - Elsevier
نوع ارائه مقاله: ژورنال
نوع مقاله: ISI
سال انتشار مقاله: 2020
ایمپکت فاکتور: 1/604 در سال 2019
شاخص H_index: 67 در سال 2020
شاخص SJR: 0/634 در سال 2019
شناسه ISSN: 0920-3796
شاخص Quartile (چارک): Q2 در سال 2019
فرمت مقاله انگلیسی: PDF
وضعیت ترجمه: ترجمه نشده است
قیمت مقاله انگلیسی: رایگان
آیا این مقاله بیس است: خیر
آیا این مقاله مدل مفهومی دارد: ندارد
آیا این مقاله پرسشنامه دارد: ندارد
آیا این مقاله متغیر دارد: ندارد
کد محصول: E14279
رفرنس: دارای رفرنس در داخل متن و انتهای مقاله
فهرست مطالب (انگلیسی)

Abstract

1- Introduction

2- Experimental method

3- Results and discussion

4- Conclusions

References

بخشی از مقاله (انگلیسی)

Abstract

The deuterium permeation behavior of palladium-coated 316L stainless steel and 430 stainless steel was studied by the gas permeability testing device in this study. The results show that the deuterium permeability of the palladium-coated 316L stainless steel tested at 350 °C∼650 °C was very close to the Forcey’s results. This way, the conformity to some other reported results has been verified for the gas permeability testing device. The deuterium permeability for the oxidized 430 stainless steel was compared with that for the palladium-coated 430 stainless steel at temperature range of 350 °C–600 °C. The deuterium permeability for the oxidized 430 stainless steel was reduced by one order of magnitude compared with that for the palladium-coated 430 stainless steel. However, the activation energy of deuterium permeation as gas form for the oxidized 430 stainless steel was almost the same as that for unoxidized 430 stainless steel.

Introduction

Zirconium hydride is used as the reactor moderator in the thermionic space nuclear power and it easily decomposes hydrogen in the operating environment. The released hydrogen penetrates into the core through the relevant structural components, affecting the physical parameters of the reactor [1]. Compared with 316L austenitic stainless steel, 430 ferritic stainless steel has the advantages of good thermal conductivity, low thermal expansion coefficient and low sensitivity to stress corrosion cracking. It is selected as one of the alternative reactor core materials for structural components of the thermionic space nuclear power. Therefore, investigating the hydrogen permeation behavior of 430 ferritic stainless steel has important engineering application value for the development of thermionic space nuclear power. A lot of research has been carried out on the preparation and properties evaluation of hydrogen isotope permeation barrier coatings for the fusion reactor. However, 316L stainless steel or low-activity ferritic/martensitic steel was used as the substrate material in most of these studies [2–15]. There are few reports on the hydrogen isotope permeation behavior of 430 ferritic stainless steel. In the present study, the deuterium permeability of palladium-plated 316L stainless steel was first tested and compared with the reported values to verify the conformity to other reported results for the gas permeability testing device. Then the deuterium permeation behavior of the palladium-plated 430 stainless steel as well as that with natural oxide film was investigated.