Showing papers in "Progress in Nuclear Energy in 2015"

TL;DR: In this article, different technologies used for the treatment and disposal of spent radioactive resins were summarized and compared, including immobilization, bituminization and plastic solidification, advanced oxidation processes (such as incineration, pyrolysis, acid boiling degradation, the Fenton or Fenton-like reaction, supercritical water oxidation and plasma technology) and super compaction.

TL;DR: Based on the extensive and comprehensive literature survey, most up-to-date progress of the research in the area of two-phase flow induced vibration in piping system are thoroughly reviewed and presented.

TL;DR: In this article, the authors focus on some impediments in the deployment of such novel designs that need to be resolved through testing and qualification of components and equipment, Research and Development (R&D), training and international collaboration.

TL;DR: In this article, the mass attenuation coefficients (μ/ρ, cm2/g) for some pellet samples produced using barite, magnetite, limonite, hematite and serpentine ores at 81, 276, 302, 356, 383,keV photons emitted from 133Ba and 121, 244, 344, 444, 778,778,keV photon emitted from 152Eu have been determined by using HPGe detector.

TL;DR: In this paper, the authors present and analyze most of the extensive literature existing on the annular two-phase flow, focusing specifically on the analysis of the main phenomena that are involved.

TL;DR: In this paper, a comprehensive literature review of experimental methods and results for corium pool heat transfer is presented, which includes influence of geometry, simulant material, heating method and layer stratification.

TL;DR: In this paper, the drift-flux correlation in nuclear thermal-hydraulic system analysis codes has been evaluated by rod bundle test data taken in FRIGG and NUPEC test facilities.

TL;DR: In this article, the authors investigated the low mass flux saturated steam discharged directly into subcooled water flow in a tee junction and used a thermal equilibrium model considering heat and mass transfer to model steam condensation using user-defined function (UDF).

TL;DR: In this paper, a thermal equilibrium model has been introduced to simulate the direct contact condensation of subsonic steam injected into a subcooled water pool has been simulated using the VOF multiphase flow model and Large Eddy Simulation (LES) turbulent flow model of FLUENT.

TL;DR: In this paper, regression analysis on the thermal properties of Al 2 O 3 /H 2 O nanofluids was made, and the growth and departure of a single bubble behavior was numerically simulated by an improved Moving Particle Semi-implicit method in different flow boiling conditions.

TL;DR: In this article, a two-fluid model coupled with improved RPI wall boiling model (CHF model) was employed to investigate the departure from nuclear boiling (DNB) phenomena in vertical pipes under extremely high heat flux by using FLUENT 14.5 code.

TL;DR: Results confirm the capacity of the developed ANN-based model to estimate a fuel rod temperature with a reasonable accuracy and evaluate the efficiency of the method first on a simulated case and on the on-line measurements obtained from a real plant.

TL;DR: Gaussian Process Regression is used to build a stochastic model of the equipment degradation evolution and applies it for prognostics and applications are shown on simulated data concerning the evolution of creep damage in ferritic steel exposed to high stress and on realData concerning the clogging of sea water filters placed upstream the heat exchangers of a BWR condenser.

TL;DR: In this paper, barium borosilicate glasses produced by using rice husk ash in the compositions xBaO:(80-x)B2O3:20RHA were prepared by melt quenching technique and investigated for their radiation shielding properties.

TL;DR: In this article, the behavior of low frequency neutron noise during the 30 years of operation of German KWU built PWRs is reviewed and the role of various factors influencing neutron noise such as sub-cooled boiling, power and enrichment uprates, fuel type and mechanical fuel assembly design is discussed.

TL;DR: In this paper, the neutronic performance of the Gas Cooled Fast Reactor (GFR)2400 was analyzed using the ERANOS and SCALE code systems for beginning-life (BOL) conditions, including excess reactivity, various reactivity effects such as depressurization, Doppler or thermal expansion effects, as well as kinetic parameters.

TL;DR: In this article, a coupled Level Set (LS) and Volume of Fluid (VOF) method with a phase change model for condensation was developed and implemented in the OpenFOAM code.

TL;DR: In this article, an overview on some recent developments of Generation IV (GEN-IV) gas cooled nuclear reactor performing in the frame of innovative symbiotic fuel cycle mainly by our research group is presented.

TL;DR: In this article, thermal and epithermal neutron beam have been designed based on Isfahan Miniature Neutron Source Reactor (MNSR) using MCNP4C Monte Carlo code to meet BNCT neutron beam criteria recommended by International Atomic Energy Agency.

TL;DR: In this paper, a novel loop heat pipe cooling system is designed for passively removing the residual heat released by the spent fuel stored in the SFP under the accidental conditions such as the station blackout.

TL;DR: In this article, a review of the imaging of nuclear fuel using ionising radiation is presented, which spans the past four decades and show how the technology has developed over that time.

TL;DR: In this article, metallurgical analysis of the ferritic-martensitic steels (12Cr-steel and T91) exposed at 400-600°C for up to 8000h in supercritical CO2 pressurized at 20MPa and at 550-m in CO2 gas at atmospheric pressure has been carried out.

TL;DR: In this article, an artificial neural network (ANN) framework was used to predict axial and radial relative power distributions (RPDs) and power peaking factor (PPF) of a VVER-1000 nuclear power plant core.

TL;DR: In this article, a thorough and complete review of the steam injector system was completed and applicability of the SI system as the passive core cooling system was discussed in details, and its design and operational mechanisms, and fundamental thermal-hydraulic theory was utilized in the analysis and experimental work.

TL;DR: In this paper, neutronics analysis for thorium based fuels (U-233 + Th, U-235 + Th and Pu-239 + Th) is carried out in a whole-core model of pebble bed FHR.

TL;DR: In this article, the effect of varying the mix parameters and hence the resulting total hydrogen content on the neutron radiation shielding characteristics of Latex Modified Concrete (LMC) mixes is studied.

TL;DR: In this paper, the conjugate gradient method (CGM) is applied to solve the two-dimensional inverse heat conduction problem (IHCP) with multi-variables, in order to estimate the unknown temperature fluctuations at the inner wall of a cross profile, the temperature fluctuations of the fluid near the inner walls, and the heat convection coefficient between fluid and the internal wall of the cross profile in the pressurizer surge line, based on experimental outer wall temperature measurements.

TL;DR: The present work proposes the development of a new tool that allows the user to make interactions inside a virtual environment, which simulates the nuclear facility's structure, in order to aid on planning action strategies to improve its security.

TL;DR: In this article, the scaling analysis for the design of a natural circulation test facility using a three-level scaling methodology was performed in a well-scaled test facility to investigate thermal hydraulic flow instabilities during the startup transients for the Purdue NMR.

TL;DR: In this article, the core thermal hydraulic response for a hypothetical severe accident caused by station blackout with failure of the steam generator safety relief valve at a Chinese pressurized reactor 1000MW power plant is summarized using MELCOR.