نوع مقاله : مقاله پژوهشی
نویسندگان
پژوهشکدۀ رآکتور و ایمنی هسته‌ای، پژوهشگاه علوم و فنون هسته‌ای، سازمان انرژی اتمی ایران، تهران
چکیده
ارزش راکتیویته میله‌های ایمنی از مهم‌ترین کمیت‌ها در طراحی، ایمنی و بهره‌برداری مطمئن از راکتورهای هسته‌ای است که با استفاده از روش‌های تجربی یا تئوری گوناگون اندازه‌گیری و محاسبه می‌شود. برای قابل اعتماد بودن جواب محاسبات، نیاز به درنظر گرفتن همه جنبه‌های مختلف مسئله از جمله هندسه، مواد، دما، تعداد نقاط شبکه، کتابخانه‌های استفاده شده و تعداد گروه‌های انرژی است. ارزش راکتیویته حالت‌های مختلف قلب یک راکتور آزمون مواد با استفاده از کد 0. 2.6 MCNPX و بسته نرم‌افزاری MTR_PC به عنوان رویکردهای احتمالاتی و یقینی محاسبه شده است. جواب‌های دو رویکرد تا 51 % با یکدیگر اختلاف دارند که قابل توجه است، بنابراین یک مطالعه جامع روی همه مولفه‌های موجود انجام شده است. تصحیح دقیق ورودی‌ها، استفاده از یک کتابخانه مشترک، تصحیح نقاط شبکه فضایی و به کاربردن گروه‌های انرژی بیشتر در روش یقینی انجام شده است. مشخص شده که اثر نقاط شبکه فضایی بیشتر از دیگر مولفه‌ها در روش یقینی است و در نهایت نتایج دو روش دارای اختلاف قابل قبول کمتر از 11% است
کلیدواژه‌ها
عنوان مقاله [English]
Control rods reactivity worth calculation using deterministic and Monte Carlo approaches for an MTR type research reactor
نویسندگان [English]
- F Khoshahval
- E Boustani
Reactor and Nuclear Safety Research School, Nuclear Science and Technology Research Institute (NSTRI), Tehran, Iran
چکیده [English]
Reactivity worth of control rods as a main parameter in different nuclear reactor fields such as safety, design, and operation that could be calculated or measured with different experimental and theoretical methods. Reliable answers in calculations necessitate taking into account different characteristics such as geometries, materials, temperatures, spatial nodes, libraries, and energy groups. Reactivity worth of different core states of a Material Testing Reactor (MTR) is calculated using MCNPX 2.6.0 code and MTR_PC package as Monte Carlo and deterministic approaches respectively. It is seen that the MTR_PC and MCNPX results has considerable differences up to 51%. Therefore, an exhaustive study is done concentrating on different involved parameters. Precise modification of inputs, applying one common library in the two approaches, correcting spatial nodes, and employing more energy groups in the deterministic approach are performed. It is determined that the effect of the spatial nodes is much more important than the other parameters in the deterministic method. Finally, results of two approaches are found to be satisfactory as discrepancy is less than 11%.
کلیدواژه‌ها [English]
- Reactivity worth
- Material Testing Reactor
- Deterministic and Monte Carlo approaches
- Library
- Energy group
- Spatial node
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