Results 81 to 90 of about 2,651,698 (166)

RELAP5 code study of ROSA/LSTF experiment on a PWR station blackout (TMLB') transient

Mechanical Engineering Journal, 2014
RELAP5 code post-test analysis was performed on one of abnormal transient tests conducted with the ROSA/large scale test facility (LSTF) simulating a PWR station blackout (SBO) transient with the TMLB' scenario in 1995.
Takeshi TAKEDA, Hideo NAKAMURA
doaj   +1 more source

Liquid metal cooled fast reactor thermal hydraulic research development: A review. [PDF]

Heliyon, 2023
Agbevanu KT, Debrah SK, Arthur EM, Shitsi E.   +3 more
europepmc   +1 more source

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

Implementation of dynamic start-up test experimental data as a main part of the nuclear code validation procedure: Developed RELAP5 model for VVER-1000

Nuclear Engineering and Technology
The main purposes of start-up tests in nuclear power plants (NPPs) are to ensure safe and reliable operation, verify system functionality, comply with regulatory requirements, optimize performance, and establish a foundation for ongoing plant operation ...
Navid Vahman, Reza Akbari
doaj   +1 more source

An Interpretable Time Series Data Prediction Framework for Severe Accidents in Nuclear Power Plants. [PDF]

Entropy (Basel), 2023
Fu Y, Zhang D, Xiao Y, Wang Z, Zhou H.
europepmc   +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 code manual. Volume 4, Models and correlations [PDF]

, 1995
The RELAP5 code has been developed for best-estimate transient simulation of light water reactor coolant systems during postulated accidents. The code models the coupled behavior of the reactor coolant system and the core for loss-of-coolant accidents and operational transients such as anticipated transient without scram, loss of offsite power, loss of
openaire   +2 more sources

RELAP5 Analysis of OECD/NEA ROSA Project Experiment Simulating a PWR Loss-of-Feedwater Transient with High-Power Natural Circulation

Science and Technology of Nuclear Installations, 2012
A ROSA/LSTF experiment was conducted for OECD/NEA ROSA Project simulating a PWR loss-of-feedwater (LOFW) transient with specific assumptions of failure of scram that may cause natural circulation with high core power and total failure of high pressure ...
Takeshi Takeda, Hideaki Asaka, Hideo Nakamura   +2 more
doaj   +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

RELAP5/MOD3 code manual: Code structure, system models, and solution methods. Volume 1 [PDF]

, 1995
The RELAP5 code has been developed for best estimate transient simulation of light water reactor coolant systems during postulated accidents. The code models the coupled behavior of the reactor coolant system and the core for loss-of-coolant accidents, and operational transients, such as anticipated transient without scram, loss of offsite power, loss ...
openaire   +2 more sources