Showing papers in "Nuclear Engineering and Design in 2011"

TL;DR: In this paper, a large set of experimental data, obtained in Russia, was analyzed and a new heat-transfer correlation for supercritical water was developed based on the experimental data obtained at the normal and improved heat transfer regimes.

TL;DR: In this paper, the residual compressive strength of RPC after heating from 200-300°C increases more than that at room temperature, but, significantly decreases when the temperature exceeds 300°C.

TL;DR: In this paper, two new correlations of single-phase friction factor for turbulent flow are proposed, one for smooth pipes and the other for both smooth and rough pipes, which is an idea replacement of the correlations of Blasius and Filonenko.

TL;DR: In this article, the present capabilities of CFD for wall boiling were investigated and the computational model used combines the Euler/Euler two-phase flow description with heat flux partitioning.

TL;DR: The CATHARE 2 as discussed by the authors is a multi-purpose multi-reactor concept system code, originally developed for best estimate calculations of thermal-hydraulic transients in Water-Cooled Reactors such as PWR, VVER or BWR.

TL;DR: In this article, the symmetry groups admitted by the corresponding boundary value problem are obtained by using a special form of Lie group transformations viz. scaling group of transformations, which depends on a Lewis number, magnetic field, Brownian motion parameter and thermophoretic parameter.

TL;DR: The European Lead Fast Reactor (ELSY) as discussed by the authors is a 600 mWe pool-type reactor cooled by pure lead, which has been developed starting from September 2006, in the frame of the EU-FP6-ELSY project.

TL;DR: In this paper, a supercritical Brayton cycle analysis code with a properties program, which has the most accurate mixture models, was developed to evaluate the effect of shifting the critical point and changes in the properties of the S-CO2 cycle.

TL;DR: In this article, the authors applied neutron radiography to study the process of water absorption of two types of concrete with different water-cement ratios, namely 0.4 and 0.6.

TL;DR: The European Research Project ACSEPT (Actinide recycling by SEParation and Transmutation) aims at contributing to the development of this strategy by studying both hydrometallurgical and pyrochemical partitioning routes.

TL;DR: In this paper, a composite coating was applied to repair the bellows eroded by liquid droplet erosion (LDE), which was observed using optical microscope (OM) and scanning electron microscopy (SEM). Microhardness of the coating was determined by Vickers hardness test.

TL;DR: The European Sodium Fast Reactor (CP ESFR) project as mentioned in this paper is a large-scale collaborative project on fast-reactor systems with the goal of achieving improved safety with in particular the achievement of a robust architecture vis a vis of abnormal situations and the robustness of the safety demonstrations.

TL;DR: In this article, a robust nonlinear model predictive control for the load-following operation problem is proposed that ensures xenon oscillations are kept bounded within acceptable limits, where the controller imposes restricted state constraints on the predicted trajectory during optimization which guarantees robust satisfaction of state constraints without restoring to a min-max optimization problem.

TL;DR: In this paper, a numerical investigation of bubble behaviors in subcooled flow boiling of water under the effect of additional inertial forces has been performed considering energy and mass transfer during phase change based on the VOF (volume-of-fluid) method.

TL;DR: The literature on clad failure has been broadly categorized under the headings LOCA and RIA as discussed by the authors, where the failure mechanisms like creep, corrosion and pellet-cloth interaction have been discussed in details.

TL;DR: The NURESIM Reference Simulation Platform for Nuclear Reactors (NURESIM) as mentioned in this paper is a reference platform for the simulation of nuclear nuclear power plants, which includes a set of software tools, physical models, generic functions and assessment results.

TL;DR: The CATHARE-3 as discussed by the authors is the current industrial version of the CATHERARE-2 code, which is used for nuclear power plant safety analysis, in simulators and in coupled simulation tools.

TL;DR: In this paper, the authors proposed new coalescence and breakup closures for the inhomogeneous MUltiple bubble Size Group (MUSIG) model, which includes coalescence due to turbulence, laminar shear, wake-entrainment and eddy-capture.

TL;DR: In this paper, the effects of partitioning and transmutation on the inventory reduction, the heat source reduction and its implications to the repository capacity and on the performance assessment of the final repository are discussed.

TL;DR: In this paper, a high-speed Particle Image Velocimetry (PIV) was used to measure axial velocity fields and the cross-section velocity fields obtained by the high speed PIV measurements revealed the unsteady and complex flow structure in the elbow.

TL;DR: In this paper, a new procedure for probabilistic seismic risk assessment of nuclear power plants (NPPs) is proposed using response-based fragility curves to represent the capacity of structural and nonstructural components of NPPs, nonlinear response-history analysis to characterize the demands on those components, and Monte Carlo simulations to determine the damage state of the components.

TL;DR: In this paper, the authors used the finite element method (FEM) based on GTN model to investigate the ductile crack growth behavior in single edge-notched bend (SENB) specimens of a dissimilar metal welded joint (DMWJ) composed of four materials in the primary systems of nuclear power plants.

TL;DR: In this paper, the authors quantify comparisons between several computational results and measurements performed during a pool fire scenario in a well-confined compartment and conclude that it is important to use more than one metric for the validation process in order to get information on the uncertainties associated with different aspects of fire safety.

TL;DR: In this paper, a fretting wear test rig employing a piezoelectric actuator has been developed, which is equipped with a heating and water circulation system for power plant steam generator.

TL;DR: In this article, the authors present the results and the main lessons learnt from Phase V of BEMUSE, an international programme promoted by the Working Group on Accident Management and Analysis (GAMA) of OECD to address the issue of the capabilities of best-estimate computational tools and uncertainty analysis.

TL;DR: Wang et al. as mentioned in this paper presented an experimental investigation into comparison of the durability of the bond between GFRP and steel bars to concrete under acid environment, and the results showed that, at the end of 75 days of conditioning duration, maximum bond strength loss of 11, 22, 17.2, 14% and 14% were observed in tap water, pH = 2, pH= 3, and pH = 4 environment, respectively.

TL;DR: The High Performance Light Water Reactor (HPLWR) as mentioned in this paper is a pressure vessel type reactor operated with supercritical water at 25MPa feedwater pressure and 500°C average core outlet temperature.

TL;DR: In this paper, the original 4-equation model of pipe conveying fluid was modified by taking the dynamic effects of fluid into account, where the shape function that always used in the finite element method was replaced by the exact wave solution of the modified four equations.

TL;DR: The FLICA-OVAP platform as discussed by the authors is a platform dedicated to core thermal-hydraulic studies, which includes both subchannel scale and CFD scale capabilities, and it can be used for numerical discretization of the convective part of the problem, while the diffusion part is discretized using a diamond-type solver, adequate for nonconforming meshes.

TL;DR: In this article, a group theoretic method is applied for solving the problem of combined effect of thermal diffusion and diffusion thermo on free convective heat and mass transfer over a porous stretching surface in the presence of thermophoresis particle deposition with variable stream conditions.