Prediction of ballooning and burst for nuclear fuel cladding with anisotropic creep modeling during Loss of Coolant Accident (LOCA)

نویسندگان

چکیده

In this study, a multi-physics modeling method was developed to analyze nuclear fuel rod's thermo-mechanical behavior especially for high temperature anisotropic creep deformation during ballooning and burst occurring in Loss of Coolant Accident (LOCA). Based on transient heat transfer nonlinear mechanical analysis, the present work newly incorporated special characteristics which include gap transfer, burnup dependent material properties, with anisotropy. The proposed tested through various benchmark analyses showed good agreements analytical solutions. From validation study cladding experiment postulates LOCA scenario, it shown that development could predict behaviors accurately capability LOCA. Moreover, order verify methodology comparison between made isotropic assumption. It found more realistic cladding.

برای دانلود باید عضویت طلایی داشته باشید

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

simulation and experimental studies for prediction mineral scale formation in oil field during mixing of injection and formation water

abstract: mineral scaling in oil and gas production equipment is one of the most important problem that occurs while water injection and it has been recognized to be a major operational problem. the incompatibility between injected and formation waters may result in inorganic scale precipitation in the equipment and reservoir and then reduction of oil production rate and water injection rate. ...

exploring motivation and english test preparation strategies of iranian pre-university candidates during and at the end of test preparation period for konkur examination

the current study aimed at investigating the relationship between motivation and test preparation strategies (tpss) used by iranian pre-university students in their preparation period for the university entrance exam (uee). due to the importance of uee in iran, this study also attempted to show its impact on these two important variables. to this end, 100 pre-university students in an iranian p...

The Analysis of TRACE/FRAPTRAN in the Fuel Rods of Maanshan PWR for LBLOCA

Fuel rod analysis program transient (FRAPTRAN) code was used to study the fuel rod performance during a postulated large break loss of coolant accident (LBLOCA) in Maanshan nuclear power plant (NPP). Previous transient results from thermal hydraulic code, TRACE, with the same LBLOCA scenario, were used as input boundary conditions for FRAPTRAN. The simulation results showed that the peak claddi...

متن کامل

ذخیره در منابع من


  با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید

ژورنال

عنوان ژورنال: Nuclear Engineering and Technology

سال: 2021

ISSN: ['1738-5733', '2234-358X']

DOI: https://doi.org/10.1016/j.net.2021.04.020