محاسبات نوترونیک قلب رآکتور VVER-1000 بوشهر و بررسی ارزش میله کنترل توسط کد MCNPX

نویسندگان

دانشگاه اصفهان

10.22052/4.2.45

چکیده

در این تحقیق اطلاعات لازم از نیروگاه هسته‌ای بوشهر جهت انجام شبیه‌سازی فراهم گردیده و محاسبات نوترونیک آن با کد MCNPX انجام شده است. سپس نتایج حاصل از کد با حداقل یکی از داده‌های تجربی مربوط به این رآکتور راستی‌آزمایی شد. در این کار با نوشتن و بکارگیری برنامه­‌ای جامع و حل آماری معادله پخش، شار نوترون به دست آمد و سپس با تعیین پارامترهای مختلفی از جمله ضریب‌تکثیر بی‌نهایت بر حسب فلوئنس، ارزش میله‌های کنترل برای گروه‌های 10 و 9 در حالت Hot Zero Power (HZP) محاسبه گردید.

کلیدواژه‌ها


عنوان مقاله [English]

Neutronic core calculations of Bushehr VVER-1000 reactor and investigating the control rod worth using MCNPX code

نویسندگان [English]

  • Mehdi Nasri Nasrabadi
  • Behzad Teimouri
  • Khodadad Akbari
چکیده [English]

In this research, required information to simulate and perform neutronic calculations for Bushehr nuclear power plant using the MCNPX code was provided. The results of the code were verified with at least one of the operational data from the reactor. In this work, by writing and implementing a comprehensive program to solve the equations of statistical distribution, neutron flux was obtained and then various parameters including the infinite multiplication factor in terms of fluence were calculated and the control rod worth for Groups 9 and 10 were calculated at Hot Zero Power (HZP) state.

کلیدواژه‌ها [English]

  • VVER-1000 reactor
  • Core neutronic calculations
  • Reactivity coefficients
  • Control rod worth
  • Hot Zero Power
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