Results 131 to 140 of about 2,939 (182)

An integrated method for the leakage fault mode diagnosis and life prediction of the reactor coolant pump. [PDF]

PLoS One
Shao Y, Kang R, Fu J, Liu J.
europepmc   +1 more source

Flow stability and distribution in horizontal serpentine tube bundles with vertical headers. [PDF]

Heliyon
Illyés V, Thanheiser S, Ettlinger F, Schulz M, Haider M.   +4 more
europepmc   +1 more source

Analysis of Fast Pressure Transients using RELAP5 and TRACE

, 2014
Simulations of water hammer transients are important e.g. regarding structural analysis of piping systems in a nuclear power plant. This project aims to validate TRACE with respect to analysis of such transients.
Lundin, Anton, Holmström, Joakim
core  

OECD NEA Sample Problem Analysis with RELAP5/MOD1-019 Computer Code

, 1983
BOCCACCINI L, ORIOLO F, GALASSI G. M, PACI, SANDRO, D'AURIA, FRANCESCO SAVERIO   +4 more
core  

Some of the next articles are maybe not open access.

Related searches:

BEPU analysis of a passive decay heat removal system with RELAP5/MOD3.3 and RELAP5-3D

Progress in Nuclear Energy, 2021
Abstract Passive safety systems are currently implemented or under consideration in several advanced nuclear plants. In the Best-Estimate Plus Uncertainty (BEPU) approach it is fundamental to qualify Best-Estimate thermal-hydraulic system codes and models for the phenomena typical of passive systems and to quantify the uncertainty of calculations. In
Fabio Alcaro, Andrea Bersano, Cristina Bertani   +2 more
exaly   +2 more sources

COBRA/RELAP5: A Merged Version of the COBRA-TF and RELAP5/MOD3 Codes

Nuclear Technology, 1992
The best-estimate thermal-hydraulic codes RE-LAP5/MOD3 and COBRA-TF were adopted to the Apollo DN 10000 workstation and subsequently merged.
Sang Yong Lee, Jae Jun Jeong, Si-Hwan Kim, Soon Heung Chang   +3 more
openaire   +2 more sources

Investigations on RELAP5-3D to RELAP5-3D Coupling Methodology by PVMEXEC

Volume 3: Thermal-Hydraulics, 2016
In the framework of a BEPU (Best Estimate Plus Uncertainty) approach within the licensing process of a nuclear power plant, the need to extend the resources of nuclear system thermal-hydraulics codes, such as RELAP5-3D, arises to allow more detailed simulations of the complex 3D reality of Nuclear Power Plants (NPPs), either under normal steady-state ...
Valeria Parrinello, Marco Lanfredini, Alessandro Petruzzi, Marco Cherubini   +3 more
openaire   +1 more source

Comparison of MYRRHA RELAP5 MOD 3.3 and RELAP5-3D Models on Steady State and PLOF Transient

Nuclear Technology, 2016
AbstractThe MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) project aims at the construction of a pool-type subcritical accelerator-driven system that could also operate a...
D. Castelliti, T. Hamidouche
openaire   +1 more source

The RELAP5-FORCE MOD2 Code, A Hydrodynamic Forcing Function Calculation Version of RELAP5

Nuclear Technology, 1990
A version of the RELAP/MOD2 code has been developed to allow the direct calculation of hydrodynamic piping load histories. The code allows the calculation of piping forcing functions to evaluate the transient thermofluid conditions. A description of this code, RELAP5-FORCE MOD2 is provided.
openaire   +1 more source

RELAP5-3D User Tools

Nuclear Technology, 2016
To support the functionality of RELAP5-3D for best-estimate reactor simulation code, a variety of utility programs were developed at Idaho National Laboratory.
openaire   +1 more source