Results 101 to 110 of about 1,865 (177)

SCDAP/RELAP5/MOD 3.1 Code Manual: Developmental assessment. Volume 5 [PDF]

, 1995
The SCDAP/RELAP5 code has been developed for best estimate transient simulation of Light Water Reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, the core, fission product released during
Hohorst, J. K., Johnsen, E. C., Allison, C. M.   +2 more
core   +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

Simulation of condensation in a closed, slightly inclined horizontal pipe with a modified RELAP5 code

, 2014
The performance of the RELAP5 thermal-hydraulic system code was analyzed in predicting very fast transient condensation processes in horizontal pipes. The code significantly underpredicted the heat transfer from the primary to the secondary side in case ...
Prasser, Horst-Michael, Freixa Terradas, Jordi, Szijártó, Rita   +2 more
core   +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

Simulation of a TRIGA Reactor Core Blockage Using RELAP5 Code

Science and Technology of Nuclear Installations, 2015
Cases of core coolant flow blockage transient have been simulated and analysed for the TRIGA IPR-R1 research reactor using the RELAP5-MOD3.3 code. The transients are related to partial and to total obstruction of the core coolant channels.
Patrícia A. L. Reis, Antonella L. Costa, Claubia Pereira, Maria Auxiliadora F. Veloso, Amir Z. Mesquita   +4 more
doaj   +1 more source

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

Accident Analysis in Research Reactors

The first Research Reactor reaches its criticality on 2nd December 1942. Nowadays, more than 300 research reactors are currently in operation. Over the past fifty years, research reactors have progressed through a variety of tasks.
Adorni, Martina
core