Thermal-Hydraulics in Uncovered Core of Light Water Reactor in Severe Core Damage Accident, (I)
نویسندگان
چکیده
منابع مشابه
Thermal-Hydraulics analysis of pressurized water reactor core by using single heated channel model
Thermal hydraulics of nuclear reactor as a basis of reactor safety has a very important role in reactor design and control. The thermal-hydraulic analysis provides input data to the reactor-physics analysis, whereas the latter gives information about the distribution of heat sources, which is needed to perform the thermal-hydraulic analysis. In this study single heated channel model as a very f...
متن کاملCore Loading Design for Bushehr Pressurized Water Reactor
The modified out-in fuel management strategy was applied to the core loading design for the first four cycles of the Bushehr (Iran-1) KWU designed Pressurized Water Reactor (PWR). The minimum peak-to-average power density was chosen as the objective function of the optimization process. Lattice homogenization and group constants generation were performed by using the LEOPARD computer code. For ...
متن کاملsuppression of coke formation in thermal cracking by coke inhibitors
the main purpose of this research was to:1.develop a coking model for thermal cracking of naphtha.2.study coke inhibition methods using different coke inhibitors.developing a coking model in naphtha cracking reactors requires a suitable model of the thermal cracking reactor based on a reliable kinetic model.to obtain reliable results all these models shall be solved simultaneously.for this pu...
15 صفحه اولComputing Atomic Density Changes of Material Composition in Operation of the Nuclear Reactor Core
The present work investigates an appropriate way to calculate the 1700 atomic density changes in the reactor operations. To automate this procedure, a computer program has been designed by C#. This program suggests a way to solve this problem which is based on the solution system of differential equations (Bitman) that it is designed according to Runge-Kutta Fehlberg method. The designed softwa...
متن کاملInfluence of Coolant Phase Separation on Event Timing During a Severe Core Damage Accident in a Generic CANDU 6 Plant
The Modular Accident Analysis Program for CANDU (MAAP4-CANDU) was developed to assess the consequences of a severe core damage progression in a CANDU nuclear power station. The results from MAAP4-CANDU analyses support Level 2 PSA activities being performed for CANDU stations. During the early stages of a severe core damage accident in a CANDU plant, the primary heat transport system (PHTS) coo...
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: Journal of Nuclear Science and Technology
سال: 1986
ISSN: 0022-3131,1881-1248
DOI: 10.1080/18811248.1986.9735055