Results 21 to 30 of about 4,217 (206)
Enabling decentralized wireless index coding in practice [PDF]
, 2019 Index coding is a problem in theoretical computer science and network information theory that studies the optimal coding scheme for transmitting multiple messages across a network to receivers with different side information.
Mahler, Timothy Austin
core +1 more source
DYN3D and CTF Coupling within a Multiscale and Multiphysics Software Development (Part I)
Energies, 2021 Understanding and optimizing the relation between nuclear reactor components or physical phenomena allows us to improve the economics and safety of nuclear reactors, deliver new nuclear reactor designs, and educate nuclear staff.
Sebastian Davies +7 more
doaj +1 more source
Benchmark of Subchannel Code VIPRE-W with PSBT Void and Temperature Test Data
Science and Technology of Nuclear Installations, 2012 This paper summarizes comparisons of VIPRE-W thermal-hydraulic subchannel code predictions with measurements of fluid temperature and void from pressurized water reactor subchannel and bundle tests. Using an existing turbulent mixing model, the empirical
Y. Sung +5 more
doaj +1 more source
CHF prediction in rod bundles using round tube data
Brazilian Journal of Radiation Sciences, 2021 The present work concerns the use of 1995 CHF table for uniformly heated round tubes, developed jointly by Canadian and Russian researchers, for the prediction of critical heat flux in rod bundles geometries.
Maria Auxiliadora Fortini Veloso +1 more
doaj +1 more source
Nuclear Engineering and Technology, 2023 MARS-KS, a domestic regulatory confirmatory code of Republic of Korea, had been developed by integrating RELAP5/MOD2 and COBRA-TF. The integration of COBRA-TF allowed to extend the capability of MARS-KS, limited to one-dimensional analysis, to multi ...
Yunseok Lee, Taewan Kim
doaj +1 more source
SERPENT/SUBCHANFLOW COUPLED BURNUP CALCULATIONS FOR VVER FUEL ASSEMBLIES [PDF]
EPJ Web of Conferences, 2021 The continuous improvement in nuclear industry safety standards and reactor designers’ and operators’ commercial goals represent a push for the development of highly accurate methodologies in reactor physics.
Ferraro Diego +6 more
doaj +1 more source
Mechanism Model of Critical Heat Flux in Bundle Based on High-precision Subchannel Code
Yuanzineng kexue jishu, 2023 Critical heat flux (CHF) is a crucial safety limit for PWR core design. Accurately predicting CHF in the core rod bundle channel can enhance the economy and safety of the reactor. Currently, the prediction of rod bundle CHF in engineering is mainly based
GUO Junliang;JIANG Li;GAO Kui;KONG Huanjun;GUI Miao;SHAN Jianqiang
doaj
Computation Alignment: Capacity Approximation without Noise Accumulation [PDF]
, 2013 Consider several source nodes communicating across a wireless network to a destination node with the help of several layers of relay nodes. Recent work by Avestimehr et al. has approximated the capacity of this network up to an additive gap.
Nazer, Bobak, Niesen, Urs, Whiting, Phil
core +1 more source
MC21/CTF and VERA multiphysics solutions to VERA core physics benchmark progression problems 6 and 7
Nuclear Engineering and Technology, 2017 The continuous energy Monte Carlo neutron transport code, MC21, was coupled to the CTF subchannel thermal-hydraulics code using a combination of Consortium for Advanced Simulation of Light Water Reactors (CASL) tools and in-house Python scripts.
Daniel J. Kelly, III +5 more
doaj +1 more source
Outage Exponent: A Unified Performance Metric for Parallel Fading Channels
, 2013 The parallel fading channel, which consists of finite number of subchannels, is very important, because it can be used to formulate many practical communication systems.
Bai, Bo +3 more
core +2 more sources