Showing papers in "Nuclear Engineering and Design in 2015"

TL;DR: In this article, the authors summarized the current state of the art on irradiated concrete, including a review of the current literature and estimated the total neutron fluence expected in biological shields in typical light water reactor (LWR) configurations.

TL;DR: In this article, the authors present an attempt to supplement the FAST code system with a novel solver characterized by tight coupling between the different equations, parallel computing capabilities, adaptive time-stepping and more accurate treatment of some of the phenomena involved in a reactor transient.

TL;DR: In this paper, an innovative micro-channel equipped with an array of airfoil fins is analyzed to evaluate its performance, and sensitivity analysis with various design parameters is performed to configure the optimal arrangement of air foil fins by using CFD analysis for Supercritical Carbon dioxide Integral Experimental Loop (SCIEL) in Korean Atomic Energy Research Institute (KAERI).

TL;DR: In this article, the applicability of BaO doped PbO-P 2 O 5 glass system as gamma ray shielding material in terms of mass attenuation coefficient and half value layer at photon energies 662, 1173 and 1332 kV was evaluated.

TL;DR: In this paper, an overview of various materials that are essential to establish advanced system feasibility and performance is discussed as well as the various natures of R&D needed to select, optimize, assess and qualify advanced materials.

TL;DR: In this article, a micromechanical approach based on the Hashin composite sphere model is presented to derive a first-order separation of the effects of radiation on cement paste and aggregate, and, also, on their interaction.

TL;DR: In this paper, an extensive experimental program of heat transfer measurements has been completed recently at the University of Ottawa's supercritical pressure test facility (SCUOL). Thermal-hydraulics tests were performed for vertical upflow of carbon dioxide in directly heated tubes with inner diameters of 8 and 22mm, at high subcritical, near-critical and supercritical pressures.

TL;DR: The THAI test facility as discussed by the authors is a 60m 3 stainless steel vessel with exchangeable internals for multi-compartment investigations, including thermal-hydraulics, hydrogen, aerosol, and iodine.

TL;DR: In this article, a meso-scale approach to modeling initiation and evolution of early intergranular cracking is presented, which is present in a number of nuclear power plant components and depends on the material (e.g. composition, heat treatment, microstructure), environment and load.

TL;DR: In this article, a direct spectra-to-spectra method is developed for generating floor response spectra (FRS), which are used as input for seismic design and assessment of secondary systems in nuclear facilities.

TL;DR: In this paper, two inner core compaction parts of sintered and HIPped composite materials were first produced and then cladded them between two outer plates by HIP process, which provided not only a lead of excellent interfacial adhesion due to the improved wettability but also an enhancement of thermal neutron shielding efficiency owing to the more uniform dispersion of B4C particles.

TL;DR: In this paper, a two-fluid model incorporating drag and non-drag forces is used to simulate the flash of initially sub-cooled water in a vertical circular converging-diverging nozzle.

TL;DR: In this paper, the authors present a model for turbulent heat flux over the complete range from natural, mixed and convection to forced convection regimes in liquid metal-cooled nuclear systems.

TL;DR: In this paper, a generalized integral transform technique (GITT) was used to analyze the dynamic behavior of pipes conveying gas-liquid two-phase flow in the dimensionless temporal variable.

TL;DR: In this paper, the authors report about oxidation and quench tests of relevant silicon carbide samples at temperatures up to 2000°C in steam atmosphere, and after the tests the samples were characterized by means of optical microscopy, scanning electron microscopy and XRD and X-ray tomography.

TL;DR: In this paper, the authors measured the neutron shielding properties of concrete samples with and without limonite ore to investigate their neutron shielding qualities using measured values, macroscopic removal cross-sections (ΣR, cm−1) have been determined experimentally and also ΣRvalues have been calculated theoretically using the elemental composition of the concrete mixes.

TL;DR: In this article, total hemispherical emissivity for Inconel 718 was measured in anticipation of its application in very high temperature gas Reactors (VHTRs).

TL;DR: In this paper, the feedback coefficient and the breeding ratio are optimized based on the fuel-tographite ratio variation for a thorium-based MSR (TMSR), and the lifetime of graphite used for the TMSR is also discussed.

TL;DR: In this paper, numerical simulation of the bubble condensation in the subcooled boiling flow is performed, where the interface between two-phase is tracked via the volume of fluid (VOF) method with continuous surface force (CSF) model, implemented in the open source OpenFOAM CFD package.

TL;DR: In this article, a Finite Element Model (FEM) of the copper-steel composite was created and validated using three point bend tests, which accurately predicts the response of the composite, including large deformation and debonding failure mechanisms.

TL;DR: TALL-3D as discussed by the authors is a liquid Lead Bismuth Eutectic (LBE) loop developed according to the requirements for the experimental data for validation of coupled STH and CFD codes.

TL;DR: In this paper, the authors extend the validation to flow in which bubbles with a broad distribution of sizes up to ∼10mm are present, but the shape of the distribution remains unchanged during the flow development.

TL;DR: A series of large scale experiments on hydrogen combustion and explosion in a semi-confined layer of uniform and non-uniform hydrogen-air mixtures in the presence of obstructions or without them was performed at the Karlsruhe Institute of Technology (KIT).

TL;DR: An improved robust formulation for constituent distribution in metallic nuclear fuels is developed and implemented into the advanced fuel performance framework BISON as mentioned in this paper, where coupled thermal diffusion equations are solved simultaneously to reanalyze the constituent redistribution in post irradiation data from fuel tests performed in Experimental Breeder Reactor-II (EBR-II).

TL;DR: In this article, the authors investigated the radiation shielding properties of a new proposed building material, a novel cement-basalt fiber mixture (CBM), and found that the attenuation coefficients of concretes with basalt fibers are not notably influenced by the addition of fibers.

TL;DR: In this paper, a characterization of oxide films formed on 316 stainless steel in high temperature, hydrogenated water was conducted, and the results showed the oxide film consists of an outer layer with oxide particles of Fe-Ni spinel and hematite, and an inner continuous layer of Fe−Cr−Ni spinels.

TL;DR: In this paper, the first experimental series of tests performed to investigate mixed convection and stratification phenomena in CIRCE HLM large pool were presented, in particular the tests concern the transition from nominal flow to natural circulation regime, typical of decay heat removal (DHR) regime.

TL;DR: In this article, the PHENIX National Convection Test (NCT) was set-up in June 2009 to validate both stand-alone system code simulations and coupled simulations using system and CFD codes.

TL;DR: The THINS project of the 7th Framework EU Program on nuclear fission safety is devoted to the investigation of crosscutting thermal hydraulic issues for innovative nuclear systems as discussed by the authors, which is a significant area of research.

TL;DR: In this paper, the effect of gas velocity on the heat transfer coefficient was investigated over a wide range of Reynolds numbers of practical importance, and it was found that an increase in coolant gas flow velocity causes an increase of heat transfer coefficients and that effect of the gas flow rate varies from laminar to turbulent flow regimes at all radial positions of the studied packed pebble-bed reactor.