Results 31 to 40 of about 4,217 (206)
ANALYSIS OF FUEL LONGTERM EFFECTS USING SUBCHANNEL CODES
Journal of Engineering, 2010 Thermohydraulic computer codes such as COBRA3C are now becoming in practical use as part of power plant licensing process. One of the areas of interest to reactor designer is the effect due to longterm operations and the changes that might occur either due to irradiation (burnup) effects or thermal stresses in the reactor.
E.A. AMIN, M.Y. ABDUL-AHAD
openaire +2 more sources
Assessment of the Subchannel Code CTF for Single- and Two-Phase Flows [PDF]
Nuclear Technology, 2018 As part of the Consortium for Advanced Simulation of Light Water Reactors, the subchannel code CTF is being used for single-phase and two-phase flow analysis under light water reactor operating con...
Xingang Zhao +3 more
openaire +2 more sources
Nuclear Engineering and Technology, 2019 The methods and performance of a pin-level nuclear reactor core thermal-hydraulics (T/H) code ESCOT employing the drift-flux model are presented. This code aims at providing an accurate yet fast core thermal-hydraulics solution capability to high ...
Jaejin Lee +2 more
doaj +1 more source
Science and Technology of Nuclear Installations, 2018 This article presents the validation of the Code for Thermal-hydraulic Evaluation of Nuclear Reactors with Plate Type Fuels (COTENP), a subchannel code which performs steady-state thermal-hydraulic analysis of nuclear reactors with plate type fuel ...
Duvan A. Castellanos-Gonzalez +3 more
doaj +1 more source
Nuclear Engineering and Technology, 2021 This work deals with the validation of a high-fidelity multiphysics system coupling the Serpent 2 Monte Carlo neutron transport code with SUBCHANFLOW, a subchannel thermalhydraulics code, and TRANSURANUS, a fuel-performance analysis code. The results for
Manuel García +10 more
doaj +1 more source
Accuracy and Uncertainty Analysis of PSBT Benchmark Exercises Using a Subchannel Code MATRA
Science and Technology of Nuclear Installations, 2012 In the framework of the OECD/NRC PSBT benchmark, the subchannel grade void distribution data and DNB data were assessed by a subchannel code, MATRA. The prediction accuracy and uncertainty of the zone-averaged void fraction at the central region of the 5
Dae-Hyun Hwang +3 more
doaj +1 more source
Power and Bandwidth Efficient Coded Modulation for Linear Gaussian Channels [PDF]
, 2010 A scheme for power- and bandwidth-efficient communication on the linear Gaussian channel is proposed. A scenario is assumed in which the channel is stationary in time and the channel characteristics are known at the transmitter.
Bouman, N.J. +3 more
core +2 more sources
On Secure Transmission over Parallel Relay Eavesdropper Channel [PDF]
, 2010 We study a four terminal parallel relay-eavesdropper channel which consists of multiple independent relay-eavesdropper channels as subchannels. For the discrete memoryless case, we establish inner and outer bounds on the rate-equivocation region.
Awan, Zohaib Hassan +2 more
core +3 more sources
IET Communications, Volume 20, Issue 1, January/December 2026.This work extends the Polyanskiy‐Poor‐Verdu (PPV) framework to lognormal wireless links. Specifically, the paper derives a closed‐form approximation for the average error probability under lognormal distribution, effectively generalizing the PPV analysis beyond the additive white Gaussian noise assumption.
Peng Du, Yuan Zhang
wiley +1 more source
Assessment of CTF boiling transition and critical heat flux modeling capabilities using the OECD/NRC BFBT and PSBT benchmark databases [PDF]
, 2011 The need to refine models for best-estimate calculations, based on good-quality experimental data, has been expressed in many recent meetings in the field of nuclear applications.
Avramova, Maria, Cuervo Gómez, Diana
core +1 more source