Results 91 to 100 of about 1,865 (177)

APPLICATION OF MCNP FOR PREDICTING POWER EXCURSION DURING LOCA IN ATUCHA-2 PHWR

, 2012
This thesis consists in the developing and application of a methodology based on MCNP code to predict power and reactivity excursions depending on different representation of physical variables.
PECCHIA, MARCO
core  

RELAP5-3D User Problems [PDF]

, 2001
The Reactor Excursion and Leak Analysis Program with 3D capability1 (RELAP5-3D) is a reactor system analysis code that has been developed at the Idaho National Engineering and Environmental Laboratory (INEEL) for the U. S. Department of Energy (DOE). The
Riemke, Richard Allan
core  

Implementation of the RRC-KI Neutron Flux Correction Methodology in the RELAP5-3D Code [PDF]

, 2003
The International Atomic Energy Agency has sponsored a program, “Accident Analysis and its Associated Training Programme for RBMK-1000 Kursk-1 NPP (Phase II)”. Under the auspices of this program, Reactor Research Centre “Kurchatov Institute” (RRC-KI) has
Fisher, J. E.
core   +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

Thermal-hydraulic calculations for a fuel assembly in a European Pressurized Reactor using the RELAP5 code

Nukleonika, 2015
The main object of interest was a typical fuel assembly, which constitutes a core of the nuclear reactor. The aim of the paper is to describe the phenomena and calculate thermal-hydraulic characteristic parameters in the fuel assembly for a European ...
Skrzypek Maciej, Laskowski R.
doaj   +1 more source

ROSA/LSTF test and RELAP5 code analyses on PWR 1% vessel upper head small-break LOCA with accident management measure based on core exit temperature

Nuclear Engineering and Technology, 2018
An experiment was performed using the large-scale test facility (LSTF), which simulated a 1% vessel upper head small-break loss-of-coolant accident with an accident management (AM) measure under an assumption of total-failure of high-pressure injection ...
Takeshi Takeda
doaj   +1 more source

Experiments at natural circulation circuit and numerical simulation with RELAP5/MOD3.3 code

, 2023
A circulação natural vem sendo um importante tópico de estudo em relação aos sistemas passivos de segurança no resfriamento do núcleo de reatores nucleares, principalmente pelo fato de ter como base a inerência das leis da Física, não dependendo de ...
Frenzel, Lucas Shimada
core   +1 more source

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 implicit steady-state initialization package for the RELAP5 computer code [PDF]

, 1995
A direct steady-state initialization (DSSI) method has been developed and implemented in the RELAP5 hydrodynamic analysis program. It provides a means for users to specify a small set of initial conditions which are then propagated through the remainder of the system.
Paulsen, M. P., Peterson, C. E., Odar, F.   +2 more
openaire   +2 more sources