بررسی مشخصات اتم‌های پس‌زدۀ اولیه (PKA) و آسیب ناشی از تابش نوترون در فولاد زنگ‌نزن 316

نوع مقاله: مقاله پژوهشی

نویسندگان

1 دانش آموخته دکترا، دانشکده فیزیک، دانشگاه اراک

2 دانشیار، پژوهشکدۀ راکتور و ایمنی هسته‌ای، پژوهشگاه علوم و فنون هسته‌ای، سازمان انرژی اتمی ایران

3 دانشیار، دانشکده فیزیک، دانشگاه اراک

4 دانش آموخته دکترا، پژوهشکدۀ راکتور و ایمنی هسته‌ای، پژوهشگاه علوم و فنون هسته‌ای، سازمان انرژی اتمی ایران

چکیده

یکی از آثار تابش­های هسته­ای در مواد، جابه‌جایی اتم­ها از جایگاه خود در شبکۀ بلوری است. برای محاسبۀ آسیب تابش نوترون باید طیف انرژی اتم‌های پس­زدۀ اولیه و همچنین توزیع زاویه­ای و مکانی آن‌ها را محاسبه کرد. برنامۀ AMTRACK به منظور محاسبۀ این اطلاعات توسعه یافته است. این برنامه با استفاده از خروجی Ptrac کد MCNPX و تحلیل آن، اطلاعات مربوط به اتم­های پس­زده را به دست می‌آورد. در این مطالعه، فولاد زنگ‌نزن 316 که یکی از مهمترین آلیاژها در ساخت محفظۀ فشار راکتور است، بررسی شده است. نوترون‌های تک انرژی keV 1 تاMeV 10 روی این فلز تابش داده شده‌اند و کسر PKA‌های تولیدی، انرژی میانگین آن‌ها، بیشینۀ انرژی PKA‌ها و میزان آسیب تابشی به دست آمده است. محاسبات با استفاده از طیف نوترون راکتور بوشهر انجام شده است. با استفاده از این روش مقدار آسیب در راکتور بوشهر (برای فولاد زنگ‌نزن 316) برابر است با (dpa/fluence) 22-10× 2/7.

کلیدواژه‌ها


عنوان مقاله [English]

Survey of Primary Knock-on Atoms Characteristics and Radiation Damage in Stainless Steel Grade 316

نویسندگان [English]

  • Ali Mohamadi 1
  • Mohsen Asadi Asadabad 2
  • Saied Hamidi 3
  • Mohamad Amin Amirkhani Dehkordi 4
1 Ph.D. in Physics. Department of Physics, Arak University
2 Associate Professor, Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute, AEOI
3 Associate Professor, Department of Physics, Arak University
4 Ph.D. in Nuclear Engineering. Institute of Reactor and Nuclear Safety, Arak University
چکیده [English]

The displacement of the atoms from their lattice sites is one of the results of neutron irradiation on materials. The primary knocked-on atoms spectrum and their angular distribution should be calculated for consideration of neutron radiation damage calculation. The AMTRACK program has been developed to calculate this information. This program extracts and analyzes information about the primary knocked-on atoms by using Ptrac output of the MCNPX code. In this study, Stainless Steel 316, one of the most important alloys in the reactor pressure vessel, is investigated. The material is irradiated by single energy neutrons of 1keV to 10MeV, the fraction of produced PKAs, their average energy, their maximum energy, and radiation damage value are calculated. The calculations are performed by using the neutron spectrum of the Bushehr reactor. Using this method, the amount of damage in the Bushehr reactor pressure vessel (for Stainless Steel 316) is equal to 7.2×10-22 (dpa/ fluence).

کلیدواژه‌ها [English]

  • Primary Knocked-on Atom
  • SRIM Code
  • AMTRACK program
  • VVER-1000
  • Stainless steel 316
 

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