Safety margin and fuel cycle period enhancements of VVER-1000 nuclear reactor using water/silver nanofluid
نویسندگان
چکیده
منابع مشابه
Study of thorium advanced fuel cycle utilization in light water reactor VVER-440
The first step in investigation of thorium fuel is evaluation of the results obtained from the spectral code for this type of fuel. The benchmark summarized by IAEA in 2003 was used for partial validation of the code HELIOS 1.9. The benchmark was focused on a comparison of the methods and basic nuclear data. Acceptable results of benchmark comparison allowed examining and comparing different ad...
متن کاملModeling the measurement of VVER-1000 reactor power by neutron and gamma radiation with MCNP code
The present study deals with a new method for measuring the power of a reactor. This method uses gamma and neutron radiation resulted from the entire reactor structure, without changing its structure (online). In terms of functionality, this method can measure the reactor power in real-time and report it instantly. In order to obtain the relationship between reactor power and gamma and neutron ...
متن کاملPrimary Loop Study of a VVER-1000 Reactor With special Focus on Coolant Mixing
In this paper a detailed model of a VVER1000 reactor pressure vessel (RPV) with the extension of simplified primary loops is presented (Loop model). The primary loop components like steam generators and pumps are modelled by the outer shapes and additional source terms for energy and momentum exchange. The RPV model part is tested without primary loops and compared with former results obtained ...
متن کاملNuclear fuel in a reactor accident.
Nuclear accidents that lead to melting of a reactor core create heterogeneous materials containing hundreds of radionuclides, many with short half-lives. The long-lived fission products and transuranium elements within damaged fuel remain a concern for millennia. Currently, accurate fundamental models for the prediction of release rates of radionuclides from fuel, especially in contact with wat...
متن کاملThermo-Hydraulic Investigation of Nanofluid as a Coolant in VVER-440 Fuel Rod Bundle
The main purpose of this study is to perform numerical simulation of nanofluids as the coolant in VVER-440 fuel rod bundle. The fuel rod bundle contains 60 fuel rods with length of 960 mm and 4 spacer grids. In VVER-440 fuel rod bundle the coolant fluid (water) is in high pressure and temperature condition. In the present Thermo-hydraulic simulation, water-AL2O3 nanofluids containing various vo...
متن کاملذخیره 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: 2018
ISSN: 1738-5733
DOI: 10.1016/j.net.2018.01.015