Study of transient CHF and post-CHF flow boiling

Soon Kyu Lee; Nicholas R. Brown; Kurt A. Terrani; Colby B. Jensen; Heng Ban; Youho Lee

Study of transient CHF and post-CHF flow boiling

Soon Kyu Lee
, Nicholas R. Brown
, Kurt A. Terrani
, Colby B. Jensen
, Heng Ban
, Youho Lee

Nuclear Fuels & Materials

Research output: Contribution to conference › Paper › peer-review

1 Scopus citations

Abstract

Flow boiling experiments were conducted for the atmospheric transient condition to gain a mechanistic understanding of Critical Heat Flux (CHF) and post-CHF behavior of tube material. Half-sine shaped pulsed power relevant to Reactivity Initiated Accident (RIA) were applied to Inconel 600 tube under various flow rates (200 to 600kg m⁻²s⁻¹). The transient onset of nucleate boiling (ONB), the departure of nucleate boiling (DNB), and rewetting points were detected by mechanistic interpretation of measured temperature and power input. Typical transient pulsed power boiling behavior was analyzed by each boiling regime covering single phase convection, nucleate boiling, film boiling, and transition back to single phase convection.

Original language	English
Pages	2177-2182
Number of pages	6
State	Published - 2019
Event	18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 - Portland, United States Duration: Aug 18 2019 → Aug 23 2019

Conference

Conference	18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019
Country/Territory	United States
City	Portland
Period	08/18/19 → 08/23/19

Keywords

Reactivity Initiated Accident
TREAT
Transient Flow Boiling

Cite this

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title = "Study of transient CHF and post-CHF flow boiling",

abstract = "Flow boiling experiments were conducted for the atmospheric transient condition to gain a mechanistic understanding of Critical Heat Flux (CHF) and post-CHF behavior of tube material. Half-sine shaped pulsed power relevant to Reactivity Initiated Accident (RIA) were applied to Inconel 600 tube under various flow rates (200 to 600kg m−2s−1). The transient onset of nucleate boiling (ONB), the departure of nucleate boiling (DNB), and rewetting points were detected by mechanistic interpretation of measured temperature and power input. Typical transient pulsed power boiling behavior was analyzed by each boiling regime covering single phase convection, nucleate boiling, film boiling, and transition back to single phase convection.",

keywords = "Reactivity Initiated Accident, TREAT, Transient Flow Boiling",

author = "Lee, \{Soon Kyu\} and Brown, \{Nicholas R.\} and Terrani, \{Kurt A.\} and Jensen, \{Colby B.\} and Heng Ban and Youho Lee",

note = "Publisher Copyright: {\textcopyright} 2019 American Nuclear Society. All rights reserved.; 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 ; Conference date: 18-08-2019 Through 23-08-2019",

year = "2019",

language = "English",

pages = "2177--2182",

}

TY - CONF

T1 - Study of transient CHF and post-CHF flow boiling

AU - Lee, Soon Kyu

AU - Brown, Nicholas R.

AU - Terrani, Kurt A.

AU - Jensen, Colby B.

AU - Ban, Heng

AU - Lee, Youho

PY - 2019

Y1 - 2019

N2 - Flow boiling experiments were conducted for the atmospheric transient condition to gain a mechanistic understanding of Critical Heat Flux (CHF) and post-CHF behavior of tube material. Half-sine shaped pulsed power relevant to Reactivity Initiated Accident (RIA) were applied to Inconel 600 tube under various flow rates (200 to 600kg m−2s−1). The transient onset of nucleate boiling (ONB), the departure of nucleate boiling (DNB), and rewetting points were detected by mechanistic interpretation of measured temperature and power input. Typical transient pulsed power boiling behavior was analyzed by each boiling regime covering single phase convection, nucleate boiling, film boiling, and transition back to single phase convection.

AB - Flow boiling experiments were conducted for the atmospheric transient condition to gain a mechanistic understanding of Critical Heat Flux (CHF) and post-CHF behavior of tube material. Half-sine shaped pulsed power relevant to Reactivity Initiated Accident (RIA) were applied to Inconel 600 tube under various flow rates (200 to 600kg m−2s−1). The transient onset of nucleate boiling (ONB), the departure of nucleate boiling (DNB), and rewetting points were detected by mechanistic interpretation of measured temperature and power input. Typical transient pulsed power boiling behavior was analyzed by each boiling regime covering single phase convection, nucleate boiling, film boiling, and transition back to single phase convection.

KW - Reactivity Initiated Accident

KW - TREAT

KW - Transient Flow Boiling

UR - https://www.scopus.com/pages/publications/85073751108

M3 - Paper

AN - SCOPUS:85073751108

SP - 2177

EP - 2182

T2 - 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019

Y2 - 18 August 2019 through 23 August 2019

ER -

Study of transient CHF and post-CHF flow boiling

Abstract

Conference

Keywords

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