Showing papers in "Progress in Nuclear Energy in 2016"

TL;DR: In this paper, the causal relationship between nuclear energy consumption, CO2 emissions, renewable energy and real GDP per capita using dynamic panel for nine developed countries over the period 1990-2013 was investigated.

TL;DR: In this paper, the neutronic performance of accident tolerant fuels (ATF) was analyzed in both pressurized and boiling water reactors, and two concepts were evaluated: (1) coating the exterior of zirconium-alloy cladding with thin ceramics to limit the zirconsium available for reaction with higher temperature steam; (2) replacing ZIRconium alloys with alternative materials possessing slower oxidation kinetics and reduced hydrogen production.

TL;DR: An overview of the reactor dynamics code DYN3D, which comprises various 3D neutron kinetics solvers, a thermal-hydraulics reactor core model and a thermo-mechanical fuel rod model, is provided.

TL;DR: In this paper, the mass attenuation coefficient (μ ρ), effective atomic number ( Z eff ), electron density ( N el ), and buildup factors have been investigated for concretes with and without magnetite aggregate.

TL;DR: In this paper, EPDM rubber with boric acid was prepared and thermal and mechanical tests were carried out and the changes in the thermal and physical properties were studied, explicitly.

TL;DR: In this article, Taguchi method and artificial neural network (ANN) were implemented to find the optimal mixture of RSC containing lead-slag aggregate using 27 concrete samples with different mixtures were fabricated and tested.

TL;DR: In this paper, the surface tension between vapor and liquid phases is considered using continuous surface force (CSF) method, and a smoothing filter is applied to improve curvature calculation.

TL;DR: In this paper, an attempt has been made to prepare binary alloys of Pb and Sn in different compositions and the physical properties of the prepared alloys viz. dimensions and density has been measured.

TL;DR: In this article, the hydrophobic membrane contactor (HMC) was adopted to remove and recover the ammonia from radioactive wastewater at room temperature, and the operating parameters such as feed velocity and initial ammonia concentration were determined.

TL;DR: The potential improvement to be studied in order to improve the overall environmental footprint of nuclear energy and its position with regards the other energy sources is depicted.

TL;DR: In this paper, large-scale COPRA experiments were performed to investigate the natural convection heat transfer in melt pools for the in-vessel retention during severe accidents in Chinese large scale advanced PWRs.

TL;DR: The COPRA test facility as mentioned in this paper is a two-dimensional 1/4 circular slice vessel with an inner radius of 2.2m and a curved vessel wall of 30mm.

TL;DR: It is proposed that implementation of INDE will lead to shorten development times, reduced costs and increased credibility, operability, reliability and safety.

TL;DR: In this article, a nonlinear dynamic model for a passively cooled small modular reactor (SMR) is developed, which includes representations for reactor core, steam generator, pressurizer, hot leg riser and downcomers.

TL;DR: Anisotropic and isotropic ablation in molten corium-concrete interaction (MCCI) phenomenon was studied with the Moving Particle Semi-implicit (MPS) method by carrying out numerical simulations of CCI-2 and 3 experiments as mentioned in this paper.

TL;DR: In this article, the authors benchmarked the density functional theory (DFT)-based ab initio methods for prediction of structural and thermochemical parameters of nuclear materials, including various actinide-bearing molecular complexes and lanthanidebearing monazite-and xenotime-type prospective ceramic nuclear waste host forms.

TL;DR: In this article, the authors used finite element analysis (FEA) to evaluate the hydraulic flow-induced impact intensity between the fuel rods and the spacer grids for grid-to-rod fretting wear mitigation.

TL;DR: In this paper, the mass attenuation coefficient (μm), the effective atomic number (Zeff) and the effective electron density (Neff) of Gd3Al2Ga3O12:Ce (GAGG) and CaMoO4 scintillators were measured at different gamma ray energies.

TL;DR: In this article, a fuel performance code for light water reactors called CityU Advanced Multiphysics Nuclear Fuels Performance with User-defined Simulations (CAMPUS) was developed.

TL;DR: In this article, the preliminary neutronic and thermal-hydraulic analysis of the TMSR-SF is performed by developing a validated 3-D model for the reactor with MCNP-4C.

TL;DR: In this paper, the results of the investigation of radioactive glassy lava-like materials formed as a result of the Chernobyl NPP accident at their current state are presented, and complementary analytical methods, such as vibrational spectroscopy, XAFS, SEM, EBSD, X-ray tomography, provide new information about structure of Chernobyl lava matrix and inclusions.

TL;DR: In this article, a transient analysis code (TAPIRS) for heat pipe cooled space reactor power system (HPS) has been developed and applied to investigate the system transient performance during a startup from zero cold power to full power.

TL;DR: In this paper, the authors provide a review on the theoretical analysis and experimental studies on flow instability in three types of natural circulation driven nuclear reactors, ranging from conventional nuclear reactors to small modular reactors.

TL;DR: In this article, a thermal hydraulic integral effect test facility, named as advanced core-cooling mechanism experiment (ACME), was used to investigate the SBLOCA transient in passive safety plants.

TL;DR: A dynamic minimum dose walking path-searching method based on the static minimum dose Walking path-planning method earlier, and path- Planning simulation platform for nuclear radiation environment with virtual reality technology to plan walking path and virtual simulation are built.

TL;DR: In this article, the authors present a review of the nuclear liability regimes currently in operation around the world, and analyse the international nuclear liability regime following the accident at Fukushima Daiichi, comparatively assesses the liability regimes for nuclear energy and the non-nuclear energy sector.

TL;DR: An implementation method of cyber security for the safety system in the development phase is suggested, which introduces specific security activities based on a practice in a nuclear facility construction project and explains experiences resolving security vulnerabilities of the system.

TL;DR: In this paper, the results of thermal-hydraulic calculations of a large break loss of coolant accident (LBLOCA) analysis for a VVER-1000/V446 unit at Bushehr nuclear power plant (BNPP) were presented.

TL;DR: In this article, the authors give short, basic information about selected methods of the corrosion reduction and corrosion inhibitors used in nuclear power plants, mainly in pressurized water reactors PWRs and boiling water reactors BWRs.

TL;DR: This paper provides the first post-Fukushima comprehensive review of AMSTs, covering the particularities of all their elements, unlike other previous review papers which are limited to the study of individual fields, such as fault detection or decision-making support.