Measurement of coolant flow in a nuclear fuel test rig

Autor:	Sung-Ho Heo, Chang-Young Joung, Sung-Ho Ahn, Jintae Hong, Jong-Bum Kim
Rok vydání:	2015
Předmět:	Engineering Nuclear fuel business.industry Mechanical Engineering Nuclear engineering Test rig Measure (physics) Industrial and Manufacturing Engineering Coolant Flow velocity Heat flux Thermocouple Heat generation sense organs Electrical and Electronic Engineering business
Zdroj:	International Journal of Precision Engineering and Manufacturing. 16:1993-1998
ISSN:	2005-4602 2234-7593
Popis:	The heat generation rate is one of the most important characteristics in evaluating the performance of nuclear fuel. The heat generation rate of a nuclear fuel rod can be measured indirectly by calculating the heat flux that coolant absorbs while passing by the nuclear fuel rod. To calculate the heat flux from the fuel rod, it is necessary to measure the temperature deviation and flow velocity at both end parts of the fuel rod. Thus, measuring the flow velocity in the test rig during the irradiation test of nuclear fuel is important to measure the heat generation rate. In this study, a cross correlation technique that uses signals obtained from two thermocouples instrumented at both end parts of the fuel rod has been developed to measure the flow velocity of coolant in the test rig.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::0a5aa1b0442c547d82122aa0859b02ef https://doi.org/10.1007/s12541-015-0259-y Zobrazit plný text záznamu Full text from SpringerLink