Showing papers in "Nuclear Engineering and Design in 2003"

TL;DR: In this paper, the authors examined the TRISO-coated fuel fabrication processes in the US and Germany and the associated irradiation database with a goal of understanding why the German fuel behaves acceptably, why the US fuel has not faired as well, and what process/production parameters impart the reliable performance to this fuel form.

TL;DR: The Pebble Bed Modular Reactor (PBMR) was developed by Eskom and partners in South Africa, and has been under development since 1994 as discussed by the authors, where the design has moved from a copy of the HTR-Modul developed in Germany to a direct gas cycle design utilising the Brayton cycle.

TL;DR: In this paper, the authors present an economic feasibility assessment of a high performance light water reactor (HPLWR) under the co-sponsorship of the European Commission and the University of Tokyo.

TL;DR: The international Phebus Fission Product (FP) programme, initiated in 1988 and performed by the French Institut de Radioprotection et de Surete Nucleaire (IRSN), investigates key phenomena of severe water reactor accidents as discussed by the authors.

TL;DR: In this article, the authors developed theoretical models for interfacial area source and sink terms for a two-group transport equation, including the shearing-off of small bubbles from slug/cap bubbles, the wake entrainment of spherical/distorted bubble group into slug and cap bubble groups, wake acceleration and coalescence between slug and Cap bubbles, and the breakup of slug/Cap bubbles due to turbulent eddy impacts.

TL;DR: In this paper, the split Hopkinson pressure bar (SHPB) technique with a special experimental apparatus was used to obtain the material behavior under high strain rate loading conditions such as seismic loading.

TL;DR: The Gas Turbine High Temperature Reactor of 300 MWe nominal capacity (GTHTR300) as mentioned in this paper was designed and developed at the Japan Atomic Energy Research Institute (JAERI).

TL;DR: The PARSOAR project as discussed by the authors is one of the scientific projects on hydrogen risk in nuclear power plants co-sponsored by the European Commission in the Fifth Euratom Framework Program and the Swiss government.

TL;DR: In this paper, a reliability study performed with reference to a passive thermohydraulic natural circulation (NC) system, named TTL-1, was performed with the main purpose to optimize the system design.

TL;DR: The Deep-Burn Transmuter as discussed by the authors uses ceramic-coated fuel particles that provide very strong containment and are highly resistant to irradiation, thereby allowing very extensive destruction levels (Deep Burn) in one pass, using gas-cooled modular helium reactor (MHR) technology developed for high-efficiency energy production.

TL;DR: An improved look-up table for film-boiling heat-transfer coefficients has been derived for steam-water flow inside vertical tubes as mentioned in this paper, which contains 77,234 filmboiling data points obtained from 36 sources.

TL;DR: The use of Computational Fluid Dynamics (CFD) for nuclear power plant safety analysis has been discussed in this article, where case studies of applications are discussed and lessons drawn.

TL;DR: A risk analysis tool is developed for computation of the distributions of fire model output variables, which is used to estimate the failure probability of redundant cables in a cable tunnel fire, and the failure and smoke filling probabilities in an electronics room during an electronics cabinet fire.

TL;DR: In this article, the sub-channel analysis code Sub-Channel Thermal-hydraulic Analysis in Fuel Assemblies under Supercritical conditions (STAFAS) has been developed, which will have a higher numerical efficiency compared to the conventional subchannel analysis codes.

TL;DR: The cost-shared project ARVI (assessment of reactor vessel integrity) involves a total of nine organizations from Europe and USA as discussed by the authors. But the work consists of experiments and analysis development.

TL;DR: In this paper, a cross-cylinder type set-up was used to perform fretting tests in room temperature water with Inconel 690 and 690 in contact with STS 304.

TL;DR: In this paper, the results of steam explosion experiments using reactor material carried out under the Test for Real cOrium Interaction with water (TROI) program are discussed.

TL;DR: In this article, the interfacial area transport equation applicable to the bubbly flow is presented and evaluated against data acquired by a state-of-the-art miniaturized double-sensor conductivity probe in an adiabatic air-water co-current vertical test loop under atmospheric pressure condition.

TL;DR: In this article, the authors used the Moving Particle Semi-Implicit (MPS) method to solve the Navier-Stokes equations for both the drops and the ambient fluid.

TL;DR: In this article, a two-group interfacial area transport model was proposed to predict the evolution of air-water upward flow in a 2-inch airwater loop with sufficient information on axial development and the radial distribution of the local parameters.

TL;DR: In this paper, a new model for upward vertical subcooled flow boiling at low pressure has been proposed, which considers the most relevant closure relationships of one-dimensional thermal-hydraulic codes that are important for accurate prediction of vapour contents.

TL;DR: In this paper, the authors describe the analysis of the basic features of the GT-MHR reactor core fueled by plutonium, and the temperature coefficient of reactivity depends both on the temperature and burnup level.

TL;DR: In this article, the critical heat flux (CHF) on a one-dimensional downward heating rectangular channel having a narrow gap was examined by changing the orientation of the copper test heater assembly.

TL;DR: In this paper, an ANN for predicting critical heat flux (CHF) under low pressure and oscillation conditions has been trained successfully for either natural circulation or forced circulation (FC) in the present study.

TL;DR: In this article, an annular nuclear core consisting of a central column of graphite spheres and a surrounding ring of fuel pebbles is employed to simulate flow and heat transport in the core and the surrounding graphite reflector.

TL;DR: In this article, the spreadability of corium-concrete mixtures having large solidification ranges even with viscous silicic melts, the change of microstructure due to cooling rates, the occurrence of a large thermal contact resistance at the corium substrate interface, the presence of a steep viscosity gradient at the surface, the transient concrete ablation.

TL;DR: In this article, a systematic methodology to guide the definition of the failure criteria of a passive system and the evaluation of its probability of occurrence, through the identification of the relevant system parameters and the propagation of their associated uncertainties, is presented.

TL;DR: In this paper, a parallel effort is devoted to model developments for severe accident (SA) computer codes, and these codes are finally used for plant calculations to assess SA code capabilities and to apply results produced in this project to evaluate their consequences on key SA sequences occurring in different plants such as PWR-1300, BWR, VVER-1000, EPR and in the TMI-2 accident.

TL;DR: In this article, a gas turbine high temperature reactor of 300 MWe nominal capacity (GTHTR300) power plant, aiming at prototype demonstration in Japan during 2010s, is described.

TL;DR: The objective of this paper is to capture as much as possible, the lessons learned during the development and coding of the fully-implicit two-phase three-field model.