Results 81 to 90 of about 362 (143)

An open time-series simulated dataset covering various accidents for nuclear power plants. [PDF]

Sci Data, 2022
Qi B, Xiao X, Liang J, Po LC, Zhang L, Tong J.   +5 more
europepmc   +1 more source

Benchmarking COMSOL Multiphysics Single-Subchannel Thermal-Hydraulic Analysis of a TRIGA Reactor with RELAP5 Results and Experimental Data

Science and Technology of Nuclear Installations, 2019
COMSOL Multiphysics has been used to conduct thermal-hydraulic analysis in multiple nuclear applications. The aim of this study is to benchmark the prediction accuracy of COMSOL Multiphysics in performing thermal-hydraulic analysis of TRIGA (Training ...
Ahmed K. Alkaabi, Jeffrey C. King
doaj   +1 more source

A review of the application of artificial intelligence to nuclear reactors: Where we are and what's next. [PDF]

Heliyon, 2023
Huang Q, Peng S, Deng J, Zeng H, Zhang Z, Liu Y, Yuan P.   +6 more
europepmc   +1 more source

RELAP5/MOD3.3 Code Validation with Plant Abnormal Event

Science and Technology of Nuclear Installations, 2008
Measured plant data from various abnormal events are of great importance for code validation. The purpose of the study was to validate the RELAP5/MOD3.3 Patch 03 computer code with the abnormal event which occurred at Krško Nuclear Power Plant (NPP) on ...
Andrej Prošek, Borut Mavko
doaj   +1 more source

Application target image of a small modular fluoride salt-cooled high temperature reactor based on the analysis of energy demand and environmental conditions in western China. [PDF]

Heliyon, 2022
Guo Y, Dai Y, Zhang J, Jiang D, Fu Y.
europepmc   +1 more source

Thermal hydraulic simulations of the Angra 2 PWR

EPJ Nuclear Sciences & Technologies, 2015
Angra 2, the second Brazilian nuclear power plant, began the commercial operation in 2001. The plant is a pressurized water reactor (PWR) type with electrical output of about 1350 MW.
González-Mantecón Javier, Costa Antonella Lombardi, Veloso Maria Auxiliadora Fortini, Pereira Claubia, de Lima Reis Patrícia Amélia, Hamers Adolfo R., Scari Maria Elizabeth   +6 more
doaj   +1 more source

Simulation of Small-Break Loss-of-Coolant Accident Using the RELAP5 Code with an Improved Wall Drag Partition Model for Bubbly Flow

Energies
The RELAP5 code is a computational tool designed for transient simulations of light water reactor coolant systems under hypothesized accident conditions.
Young Hwan Lee, Nam Kyu Ryu, Byoung Jae Kim   +2 more
doaj   +1 more source

二次开发的RELAP5在倾斜条件下对PRS运行分析的适用性研究

He jishu
为验证经二次开发后的RELAP5程序在倾斜条件下的适用性，基于缩小比例的反应堆二次侧非能动余热排出系统（Passive Residual Heat Removal System，PRS）实验装置，开展了倾斜角度为-24°~+24°的工况下的余热排出实验。在此基础上，使用二次开发后的RELAP5程序对实验工况进行了模拟计算，利用实验数据验证其适用性，并进行了进一步对比分析。研究结果表明：二次开发后的RELAP5程序能有效预测倾斜条件下系统运行特性的变化 ...
郝 承明, 赵 京, 汪 涛, 梁 铁波, 汪 宇, 徐 慧天, 孙 燕, 喻 巧, 张 皓   +8 more
doaj   +1 more source

Steam generator identification using piecewise affine model

Results in Nonlinear Analysis, 2019
The role of steam generators in power plants is to remove the thermal power produced in the first cycle and provide the turbine intake steam. Controlling the steam generator water level has an important role in preventing unwanted turbine trips and ...
Samaneh Sadat Sajjadi, Amin Jajarmi, Ahamad Hajipour
doaj  

Numerical simulation of heat dissipation characteristics in PWR high-pressure coolant pipes during cold shutdown. [PDF]

Sci Rep
Tang F, Wang W, Luo Y, Chen Y, Yan B, Liu S.   +5 more
europepmc   +1 more source