Results 101 to 110 of about 2,939 (182)

Evaluation of Relap5 Reactor Core Modeling Capability

, 2001
of Thesis Presented to the Graduate School of the University of Florida in Partial Fulfillment of the Requirements for the Degree of Master of Science EVALUATION OF RELAP5 REACTOR CORE MODELING CAPABILITY By Vincent J.-P.
Vincent J. -p. Roux
core  

RELAP5 code development and assessment at the Savannah River Site [PDF]

, 1991
Over the past year, the focus of RELAP5 use at the Savannah River Site has been on code applications to reactor accidents having a direct bearing on setting power limits, with a lesser emphasis on code development. In the applications task, RELAP5/MOD2.5
Dimenna, R. A.
core  

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

High Fidelity, Real Time Simulation With Relap5/nestle

, 2007
This paper will focus on the enhancements to RELAP5 to achieve real-time performance.
Judd Inel
core  

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  

Streamlining of the RELAP5-3D Code [PDF]

, 2007
RELAP5-3D is widely used by the nuclear community to simulate general thermal hydraulic systems and has proven to be so versatile that the spectrum of transient two-phase problems that can be analyzed has increased substantially over time. To accommodate
Hykes, Joshua, Mesina, George L, Guillen, Donna Post   +2 more
core  

ICONE-22450 RELAP5-3D CODE APPLICATION FOR RBMK-1500 REACTOR CORE ANALYSIS [PDF]

, 2020
The paper presents an evaluation of RELAP5-3D code suitability to model specific transients that take place during RBMK-1500 reactor operation, where the neutronic response of the core is important.
Evaldas Bubelis, Algirdas Kaliatka, Eugenijus Uspuras   +2 more
core  

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