Results 91 to 100 of about 375,932 (182)
HTR-United/htr-united: v0.1.119
<p>Version 0.1.119</p> <p><strong>Full Changelog</strong>: https://github.com/HTR-United/htr-united/compare/v0.1.118...v0.1.119</p ...
Jan Hajič jr. +17 more
core +1 more source
Compact Engineering Simulator for HTR-PM by Embedding THERMIX Code in vPower Simulation Platform
, 2010 This paper describes the development of a compact engineering simulator of Pebble-bed Modular High Temperature Gas-cooled Reactor (HTR-PM) by embedding THERMIX code into the vPower simulation environment.
Yuanle Ma +5 more
core +1 more source
Thermal-hydraulic Code Development and Analysis of HTGR Helical Tube Supercritical Steam Generator
Yuanzineng kexue jishu, 2022 Supercritical steam generator can further improve the power generation efficiency of high temperature gas-cooled reactor (HTGR). A supercritical steam generator design is proposed based on the experience of the subcritical once through steam generator ...
FAN Hongyi;LI Xiaowei;WU Xinxin;SUN Libin
doaj
HTR-United/htr-united: v0.1.123
<p>Version 0.1.123</p> <p><strong>Full Changelog</strong>: https://github.com/HTR-United/htr-united/compare/v0.1.122...v0.1.123</p ...
Jan Hajič jr. +17 more
core +1 more source
A Study on the Instantaneous Turbulent Flow Field in a 90-Degree Elbow Pipe with Circular Section
Science and Technology of Nuclear Installations, 2016 Based on the special application of 90-degree elbow pipe in the HTR-PM, the large eddy simulation was selected to calculate the instantaneous flow field in the 90-degree elbow pipe combining with the experimental results.
Shiming Wang +4 more
doaj +1 more source
HTR-United/htr-united: v0.1.111
<p>Version 0.1.111</p> <p><strong>Full Changelog</strong>: https://github.com/HTR-United/htr-united/compare/v0.1.110...v0.1.111</p ...
Jan Hajič jr. +16 more
core +1 more source
SCALE ANALYSIS OF DECAY HEAT REMOVAL SYSTEM BETWEEN HTR-10 AND HTR-PM REACTORS UNDER ACCIDENTAL CONDITIONS [PDF]
, 2017 The 10 MW high-temperature gas-cooled test module (HTR-10) is a graphite-moderated and helium-cooled pebble bed reactor prototype that was designed to demonstrate the technical and safety feasibility of this type of reactor project under normal and ...
ALVIM, Antonio C. M +2 more
core
HTR-United/htr-united: v0.1.117
<p>Version 0.1.117</p> <p><strong>Full Changelog</strong>: https://github.com/HTR-United/htr-united/compare/v0.1.116...v0.1.117</p ...
Jan Hajič jr. +17 more
core +1 more source
A Nodal Dynamic Model for Control System Simulation of the HTR-PM Reactor Core
, 2010 The modular high-temperature gas-cooled nuclear reactor (MHTGR) is seen as one of the best candidates for the next generation of nuclear power plants.
Zhe Dong, Xiaojin Huang, Liangju Zhang
core +1 more source
Loss of forced cooling accident analysis of HTR-PM using MELCOR 2.2 code
, 2018 This MELCOR 2.2 severe accident was used to study two accident scenarios in the Chinese high temperature reactor HTR-PM. A model of the reactor core, thermal insulator and metal structures, reactor pressure vessel and the residual heat removal system was
Kalilainen, Jarmo (author) +2 more
core +1 more source