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Showing papers in "Annals of Nuclear Energy in 2015"


Journal ArticleDOI
TL;DR: The capabilities and physics models implemented inside the FLUKA code are briefly described, with emphasis on hadronic interaction as discussed by the authors, and examples of the performances of the code are presented including basic (thin target) and complex benchmarks, and radiation detector specific applications.

521 citations


Journal ArticleDOI
TL;DR: An overview of OpenMC, an open source Monte Carlo particle transport code recently developed at the Massachusetts Institute of Technology, which uses continuous-energy cross sections and a constructive solid geometry representation, enabling high-fidelity modeling of nuclear reactors and other systems.

390 citations


Journal ArticleDOI
TL;DR: SuperMC as mentioned in this paper is a CAD-based Monte Carlo program for integrated simulation of nuclear systems by making use of hybrid MC and deterministic methods and advanced computer technologies, which can perform neutron, photon and coupled neutron and photon transport calculation, geometry and physics modeling, results and process visualization.

305 citations


Journal ArticleDOI
TL;DR: An overview of TRIPOLI-4®, the fourth generation of the 3D continuous-energy Monte Carlo code developed by the Service d’Etudes des Reacteurs et de Mathematiques Appliquees at CEA Saclay is presented.

225 citations


Journal ArticleDOI
TL;DR: Validation results of criticality calculation, burnup calculation, source convergence acceleration, tallies performance and parallel performance shown in this paper prove the capabilities of RMC in dealing with reactor analysis problems with good performances.

203 citations


Journal ArticleDOI
TL;DR: Examples based on the KAIST-3A benchmark core, as well as a simplified Westinghouse AP-1000 configuration, demonstrate the power of this new framework for tackling—in a coupled, multiscale manner—crucial reactor phenomena such as CRUD-induced power shift and fuel shuffle.

165 citations


Journal ArticleDOI
TL;DR: In this article, the neutronics of alternate cladding materials in a pressurized water reactor (PWR) environment were analyzed and the associated neutronics penalty/advantage, changes in reactivity coefficients, and spectral variations once a transition in the cladding was made.

152 citations


Journal ArticleDOI
TL;DR: In this paper, a mixed concrete with 39.195% magnetite Fe 3 O 4 and 15.678% lead oxide PbO, named Concrete 6 in this study, has shown the best mass attenuation coefficient, exposure buildup factor and HVL values among other mixes thus minimizing the exposure rate to the acceptable levels.

111 citations


Journal ArticleDOI
TL;DR: In this article, a collision history-based approach to sensitivity/perturbation calculations in the Monte Carlo code SERPENT is discussed, allowing the calculation of the effects of nuclear data perturbation on several response functions: the effective multiplication factor, reaction rate ratios and bilinear ratios (e.g., effective kinetics parameters).

90 citations


Journal ArticleDOI
TL;DR: In this paper, an optimized FeCrAl cladding design from a detailed parametric study in literature is adopted, which suggests reducing the cladding thickness and slightly increasing the fuel enrichment.

88 citations


Journal ArticleDOI
Rui Zhang1, Tenglong Cong1, Wenxi Tian1, Suizheng Qiu1, Guanghui Su1 
TL;DR: In this article, a two-fluid model coupled with wall boiling model was adopted to investigate two-phase forced convection subcooled boiling process in a vertical heated pipe based on FLUENT 14.5.

Journal ArticleDOI
TL;DR: In this article, the total mass attenuation coefficient (μ t ) for eight shielding materials has been calculated by using WinXCOM program in the energy range from 1-keV to 100-GeV.

Journal ArticleDOI
TL;DR: In this paper, the authors explored the potential of very small modular type high temperature gas-cooled Reactor (HTGR) with a special attention given to the power conversion system, and investigated how helium Brayton cycle performance can be affected by the component level performance and how the optimal operating condition shifts when the system size reduces.

Journal ArticleDOI
TL;DR: In this article, studies on the uptake of naturally occurring radionuclides by rice from soil of widely rice cultivated areas in Malaysia have been performed under normal field environments in order to evaluate various radiation hazards via rice consumption.

Journal ArticleDOI
TL;DR: In this paper, anion exchange resin was used to evaluate the adsorption of uranium from sulphate solutions using Amberlite IRA-402 resin and the results confirmed that the equilibrium data tend to follow Freundlich isotherm model.

Journal ArticleDOI
TL;DR: Multi-Criteria Decision Analysis was applied during the selection of nuclear power plants site using GIS software and the El Dabaa site was found to be most suitable, followed by the East El Negila site on the Mediterranean Sea.

Journal ArticleDOI
TL;DR: In this paper, a comparative evaluation of alternative compact heat exchanger designs for use as the intermediate heat exchangers in advanced nuclear reactor systems is presented, and the wavy channel PCHE with a 15° pitch angle was found to offer optimum combination of heat transfer coefficient, compactness and pressure drop as compared to other alternatives.

Journal ArticleDOI
TL;DR: MC21 as mentioned in this paper is a continuous energy Monte Carlo radiation transport code for the calculation of the steady-state spatial distributions of reaction rates in three-dimensional models, which is designed and optimized to support large-scale problems in reactor physics, shielding, and criticality analysis applications.

Journal ArticleDOI
TL;DR: The proposed model could be used to achieve a stable prediction effect with high prediction accuracy for the prediction of fluctuating data and validated by predicting such time series of NPP operating parameters as coolant void fraction, water level in SG and pressurizer.

Journal ArticleDOI
TL;DR: In this article, a Computational Fluid Dynamic (CFD) model and analysis of a HI-STORM 100S cask with FLUENT 14.0 was presented.

Journal ArticleDOI
TL;DR: In this paper, a verification of the AP1000 LBLOCA analysis by means of TRACE V5.0 patch 2 thermal-hydraulic code with the support of DAKOTA code for uncertainty calculations is presented.

Journal ArticleDOI
TL;DR: In this paper, a methodology for studying the impact of cooling water temperature on the thermal performance of a nuclear power plant (NPP) was presented, and the main findings were that an increase of one degree Celsius in temperature of the coolant extracted from environment is forecasted to decrease by 0.444% and 0.152% in the power output and the thermal efficiency of the nuclear-power plant considered, respectively.

Journal ArticleDOI
TL;DR: Specific features of the implementation of the IFP algorithm in the reference Monte Carlo code TRIPOLI-4 developed at CEA are described and the impact of nuclear data libraries, IFP cycle length and inter-cycle correlations are analyzed in detail.

Journal ArticleDOI
TL;DR: The results confirm that the proposed fuzzy probability based fault tree analysis is feasible to propagate and quantify epistemic uncertainties in fault treeAnalysis.

Journal ArticleDOI
TL;DR: Based on the analysis of two-phase thermosyphon loops, a complete design of a passive cooling system for the spent fuel pool was proposed in this article, where an analysis method for decoupling of the thermo-hydraulics of the water natural circulation in spent fuel swimming pool, two phase flow of ammonia in thermosynhphon loop and air natural flow in cooling tower was presented.

Journal ArticleDOI
TL;DR: In this paper, during a severe accident of a light water reactor (LWR), molten corium could fall in the form of jet into a water pool and the jet fragmentation is crucial process during fuel coolant int...

Journal ArticleDOI
TL;DR: In this paper, the authors investigated the effect of flow direction on heat transfer in a narrow annulus with vertically upward and downward flows and found that heat transfer is much improved in the downward flow compared to that of upward flow at high q/G ratios.

Journal ArticleDOI
Axel Hoefer1, Oliver Buss1, Maik Hennebach1, Michael Schmid1, Dieter Porsch1 
TL;DR: MOCABA as discussed by the authors is a combination of Monte Carlo sampling and Bayesian updating algorithms for the prediction of integral functions of nuclear data, such as reactor power distributions or neutron multiplication factors.

Journal ArticleDOI
TL;DR: A model to predict the strength of RSC is established using a least squares-support vector machine (LS-SVM) through grid search algorithm, and the predicted results can be adopted as an important reference for RS engineering design.

Journal ArticleDOI
TL;DR: While Serpent 2/SUBCHANFLOW’s performance in terms of physics and numerical efficiency is found to be generally satisfactory, options to further improve the coupled tool concerning both aspects are discussed.