نتایج جستجو برای: thermal hydraulics

تعداد نتایج: 218671  

2014
Vijay S. Mahadevan Elia Merzari Timothy Tautges Rajeev Jain Aleksandr Obabko Michael Smith Paul Fischer

An integrated multi-physics simulation capability for the design and analysis of current and future nuclear reactor models is being investigated, to tightly couple neutron transport and thermal-hydraulics physics under the SHARP framework. Over several years, high-fidelity, validated mono-physics solvers with proven scalability on petascale architectures have been developed independently. Based...

2012
A. Keresztúri

As a logical continuation of the former benchmark activity of AER devoted to the VVER reactor physics [1-3], now there is a rather large interest of the Kalinin-3 benchmark recently completed and published by the Nuclear Energy Agency (NEA) of the Organization for Economic Cooperation and Development (OECD) [4]. The goals of these exercises were the evaluation of the prediction capability of ad...

2009
D. Noordam A. Blom H. van der Klis

Data of flume experiments with bed forms are used to analyze and compare different roughness predictors. In this study, the hydraulic roughness consists of grain roughness and form roughness. We predict the grain roughness by means of the size of the sediment. The form roughness is predicted by three approaches: Van Rijn (1984), Vanoni & Hwang (1967) and Engelund (1966). The total roughness val...

2008
Y. Wu H. Chen J. Jiang S. Liu Y. Bai Y.Chen M. Jin Y. Liu M. Wang Y. Hu

The fusion-fission hybrid system has the potential attractiveness of good safety performances and plenty of fuel compared to the fission reactor system and also easing the requirement of fusion plasma technology. It is a practical path to the early fusion application for energy production. In this paper, a fusion-driven subcritical reactor for energy multiplier, named FDS-EM, is proposed. It ca...

1998
A. Hassanein I. Konkashbaev

Surface and structural damage to plasma-facing components (PFCs) due to the frequent loss of plasma con®nement is a serious problem for the tokamak reactor concept. The plasma energy deposited on these components during loss of con®nement causes signi®cant surface erosion, possible structural failure, and frequent plasma contamination. Surface damage consists of vaporization, spallation, and li...

2009
Timothy J. Tautges Alvaro Caceres

Reactor simulation depends on the coupled solution of various physics types, including neutronics, thermal/hydraulics, and structural mechanics. This paper describes the formulation and implementation of a parallel solution coupling capability being developed for reactor simulation. The coupling process consists of mesh and coupler initialization, point location, field interpolation, and field ...

2012
H. C. Odoi E. H. K. Akaho B. J. B. Nyarko

The core conversion studies of the Ghana Research Reactor Core started in 2006 and with the objective of designing an LEU core with similar operational capabilities as the original HEU core and with acceptable safety margins under both normal and accident conditions. Steadystate studies for converting the Ghana MNSR facility from HEU to LEU core have been performed using the PLTEMP/ANL V4.1 cod...

2012
M. Labois J. Panyasantisuk T. Höhne S. Kliem D. Lakehal

This contribution aims at introducing a new multiscale, multicomponent CFD/CMFD approach for the simulation of thermal-hydraulics flows evolving in complex component-scale configurations. In this novel approach, the flow system could involve one or two fluids, convective and conductive heat transfer in solids, and phase-change heat transfer. This is made possible thanks to the Immersed Surfaces...

1998
C.P.C. Wong E. Chin T. W. Petrie E. E. Reis M. Tillack X. Wang I. Sviatoslavsky S. Malang D. K. Sze

The ARIES-RS divertor system is selected and analyzed. A radiative divertor approach using Ne as the radiator is chosen to reduce the maximum heat flux to B6 MW m. A 2 mm W layer is used to withstand surface erosion allowing a design life close to 3 full-power-years. This W coating on the V-alloy structure is castellated to meet structural design limits. A detailed description of the calculated...

2009
S. Bhartiya P. Dufour F. J. Doyle Pascal Dufour Sharad Bhartiya Francis J. Doyle

"Thermal-hydraulic digester model using a higher order numerical method", Unpublished AIChE shall not be responsible for statements or opinions contained in papers or printed in its publications. Abstract This paper presents a detailed fundamental model of a continuous pulp digester developed for simulation and control. Most modeling efforts in the past have either emphasized on reaction kineti...

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