contributor author | Wu, Yongyong | |
contributor author | Ren, Cheng | |
contributor author | Li, Rui | |
contributor author | Yang, Xingtuan | |
contributor author | Tu, Jiyuan | |
contributor author | Jiang, Shengyao | |
date accessioned | 2019-02-28T11:05:49Z | |
date available | 2019-02-28T11:05:49Z | |
date copyright | 5/16/2018 12:00:00 AM | |
date issued | 2018 | |
identifier issn | 2332-8983 | |
identifier other | ners_004_03_031006.pdf | |
identifier uri | http://yetl.yabesh.ir/yetl1/handle/yetl/4252634 | |
description abstract | The effective thermal diffusivity and conductivity of pebble bed in the high temperature gas-cooled reactor (HTGR) are two vital parameters to determine the operating temperature and power in varisized reactors with the restriction of inherent safety. A high-temperature heat transfer test facility and its inverse method for processing experimental data are presented in this work. The effective thermal diffusivity as well as conductivity of pebble bed will be measured at temperature up to 1600 °C in the under-construction facility with the full-scale in radius. The inverse method gives a global optimal relationship between thermal diffusivity and temperature through those thermocouple values in the pebble bed facility, and the conductivity is obtained by conversion from diffusivity. Furthermore, the robustness and uncertainty analyses are also set forth here to illustrate the validity of the algorithm and the corresponding experiment. A brief experimental result of preliminary low-temperature test is also presented in this work. | |
publisher | The American Society of Mechanical Engineers (ASME) | |
title | Method and Validation for Measurement of Effective Thermal Diffusivity and Conductivity of Pebble Bed in High Temperature Gas-Cooled Reactors | |
type | Journal Paper | |
journal volume | 4 | |
journal issue | 3 | |
journal title | Journal of Nuclear Engineering and Radiation Science | |
identifier doi | 10.1115/1.4039035 | |
journal fristpage | 31006 | |
journal lastpage | 031006-10 | |
tree | Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 003 | |
contenttype | Fulltext | |