Results 21 to 30 of about 375,932 (182)
Physical Analysis of the Initial Core and Running-In Phase for Pebble-Bed Reactor HTR-PM
The pebble-bed reactor HTR-PM is being built in China and is planned to be critical in one or two years. At present, one emphasis of engineering design is to determine the fuel management scheme of the initial core and running-in phase.
Jingyu Zhang, Fu Li, Yuliang Sun
doaj +1 more source
HTR-United/htr-united: v0.1.89
<p>Version 0.1.89</p> <p><strong>Full Changelog</strong>: https://github.com/HTR-United/htr-united/compare/v0.1.88...v0.1.89</p ...
Jan Hajič jr. +15 more
core +1 more source
FISSION YIELD UNCERTAINTY PROPAGATION IN MULTI-PASS REFUELING PEBBLE-BED HTGR [PDF]
Multi-pass refueling scheme is a highlighted feature of pebble bed HTGR which spatially mixes the burnup calculation inside core. Such refueling scheme relate burnup calculation in one region of the core to others and thus affects the uncertainty ...
Wang Yizhen +3 more
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High-Fidelity MC-DEM Modeling and Uncertainty Analysis of HTR-PM First Criticality
A high-fidelity model for the first criticality of pebble-bed reactor HTR-PM is built using Monte Carlo (MC) code RMC and discrete element method (DEM) code LAMMPS.
Ruihan Li +4 more
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Operation optimization of auxiliary electric boiler system in HTR-PM nuclear power plant
Electric boilers (EBs) are the backup steam source for the auxiliary steam system of high-temperature gas-cooled reactor nuclear power plants. When the plant is in normal operations, the EB is always in hot standby status.
Xingxuan Du +4 more
doaj +1 more source
HTR-United/htr-united: v0.1.92
<p>Version 0.1.92</p> <p><strong>Full Changelog</strong>: https://github.com/HTR-United/htr-united/compare/v0.1.91...v0.1.92</p ...
Jan Hajič jr. +15 more
core +1 more source
Current radiation protection methodology offers abundant experiences on light-water reactors, but very few studies on high temperature gas-cooled reactor (HTR).
Chengxiang Guo +4 more
doaj +1 more source
Safety analysis of nuclear power plant (NPP) especially in accident conditions is a basic and necessary issue for applications and commercialization of reactors. Many previous researches and development works have been conducted.
Quanquan Guo +3 more
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Adsorption Behaviors of Cobalt on the Graphite and SiC Surface: A First-Principles Study
Graphite and silicon carbide (SiC) are important materials of fuel elements in High Temperature Reactor-Pebble-bed Modules (HTR-PM) and it is essential to analyze the source term about the radioactive products adsorbed on graphite and SiC surface in HTR ...
Wenyi Wang +3 more
doaj +1 more source
The accurate prediction of the neutronic and thermal-hydraulic coupling system transient behavior is important in nuclear reactor safety analysis, where a large-scale nonlinear coupling system with strong stiffness should be solved efficiently.
Yingjie Wu +7 more
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