Showing papers in "Annals of Nuclear Energy in 2019"

TL;DR: The methods used in the current version of NECP-Atlas are described and the performance and accuracy of the code is demonstrated on a variety of benchmarks.

TL;DR: In this paper, multi-arc ion plating under different gas pressures and bias potentials was used to obtain a reduction in the oxidation weight gain of Zircaloy by 93.35%.

TL;DR: In this paper, a new energy deposition treatment for the Serpent 2 Monte Carlo transport code is introduced, implemented as a set of energy deposition modes, each of which offers a different combination of accuracy and required computational time.

TL;DR: In this paper, a group-wise reduced-order model based on a Proper Orthogonal Decomposition (POD) technique is presented for parameterized multi-group diffusion k-eigenvalue problems.

TL;DR: In this paper, the fuel cycle and neutronics analysis of a design expected to be similar to the Westinghouse eVinci™ heat pipe (HP) reactor was presented, where low enriched urania rods and potassium liquid metal-cooled HPs were used to remove heat from the core.

TL;DR: A rapid nuclide identification method based on convolutional neural network which has high recognition accuracy for low count rate gamma-ray spectra and which can be used to improve the identification performance of rapid radiation monitoring.

TL;DR: In this article, the authors analyzed the deformation and fragmentation of the bubbles in a venturi tube under different Reynolds number and particle image velocimetry (PIV) technique.

TL;DR: In this paper, an analytical formula f(x,s) including the fuel exposure (s) and the relative radial (x) is proposed to describe the radial properties for all five kinds of fuel-cladding combinations.

TL;DR: In this article, the load-following of a typical PWR is considered based on the two-point kinetic model and constant axial offset (AO) power-distribution strategy, and the power level is controlled by the PIDs, which are tuned by a real-coded GA with decision variables include the integral of time-weighted absolute error (ITAE) and a stability condition.

TL;DR: It is demonstrated that event-based algorithms significantly outperform a history-based approach for continuous-energy transport as a result of increased device occupancy and reduced thread divergence.

TL;DR: PANGU as discussed by the authors is a modern computer code for pebble-bed High Temperature Gas-cooled Reactor (HTGR) physics analyses and fuel cycle simulations, developed by Institute of Nuclear and New Energy Technology (INET), Tsinghua University.

TL;DR: A 5-layer DRNN with rectifier linear unit activation function in neurons of the hidden layers was developed, and 12 postulated accidents plus the normal operation condition were used for a Brazilian pressurized water reactor (PWR).

TL;DR: In this article, the authors reviewed the research progress and significant achievements of the flow and rupture characteristics of the liquid film on corrugated plate wall, and summarized the shortcomings of past research and prospects for future research.

TL;DR: In this article, a Python package, SaltProc, is introduced to simulate Molten Salt Breeder Reactor (MSBR) online reprocessing by modeling the changing isotopic composition of MSR fuel salt.

TL;DR: In this paper, the authors studied the hydraulic characteristics of a gas-liquid two-phase mixing operating state of a reactor coolant pump and analyzed the laws of gas volume distribution in the overall fluid area with different gas fractions in different operating conditions.

TL;DR: In this paper, a detailed fuel-clad analysis of U3Si2-SiC during normal operation is presented, where the dependence of thermomechanical properties for each SiC layer on temperature and neutron fluence is considered in the BISON fuel performance code.

TL;DR: In this paper, the corrosion resistances of candidate materials (including ferritic/martensitic (F/M) steel, austenitic stainless steel, alumina-forming AFA stainless steel and oxide dispersion strengthened (ODS) steel) are discussed and analyzed.

TL;DR: In this article, the authors presented a coupled neutronic/thermal-hydraulic (TH) hot channel analysis of a HPD 375 MWth soluble-boron-free PWR core using 19.25% 235U enriched micro-heterogeneous ThO2-UO2 duplex fuel.

TL;DR: In this paper, three plates and channels were modeled to represent parallel channels in a fuel assembly, and six cases with various blistering distribution were simulated to investigate its influence on pressure drop, mass flow distribution, and fuel temperature.

TL;DR: Gaussian learning algorithms/kernel functions/activation functions are appropriate choices for NPPs parameters forecasting, and learning algorithms based on Gaussian distribution function are more precise for time series prediction.

TL;DR: The results show that the similar convergence rate is achieved for nonlinear and linear preconditioning in the transient neutronics/thermal-hydraulics coupling problem.

TL;DR: In this article, a Molten Salt Reactor specific depletion code (MODEC) was developed to handle its specific burnup characteristics, and three different methods were implemented in MODEC to solve the nonhomogeneous burnup equations in the continuously refueling problems.

TL;DR: In this article, the continuous energy Reactor Monte Carlo code RMC was coupled to the subchannel code CTF to analyze VERA benchmark Problem 9 for the depletion of the fuel and burnable absorbers in a typical 18-month fuel cycle.

TL;DR: It has been demonstrated that the control systems with these optimum parameters can keep good balance between maximizing control performance and minimizing control cost of the pressurizer, which contributes to the improvement of system responses with reduced mechanical wear and fatigue risk of corresponding actuators.

TL;DR: In this article, a numerical model to simulate nuclear structural behaviors in earthquake is validated by comparison with data from a previous study on a nonlinear dynamic analysis of a reinforced concrete shield building, which is then used to carry out a series of parametric analyses with 112 computational cases so as to determine influence of strong aftershocks on structural elastic-plastic behavior considering input of threedimensional ground motions.

TL;DR: In this article, the specific heat capacity of the compacted Gyeongju bentonite buffer material was measured using a dual probe method for varying degrees of saturation and dry densities.

TL;DR: Genetic programming was proven to be a methodology capable of attaining success rates of, or very close to, 100%, with quite simple parameterization of the algorithm and at a very reasonable time, putting itself in levels of performance similar or even superior to other similar systems available in the scientific literature.

TL;DR: In this article, the presence of helium bubbles in the core of the Molten Salt Fast Reactor (MSF Reactor) is investigated from both a neutronics and thermal-hydraulics point of view.

TL;DR: The transient methodology of the Transient Multilevel (TML) Method used in the MPACT code was verified using Phase I of the recently developed OECD/NEA C5G7-TD benchmark, which was specifically designed for validating the transport space-time simulations.