Flow blockage analysis of a channel in a typical material test reactor core

Qing Lu; Suizheng Qiu; G. H. Su

doi:10.1016/j.nucengdes.2008.06.016

Flow blockage analysis of a channel in a typical material test reactor core

Qing Lu
, Suizheng Qiu
, G. H. Su

School of Energy and Power Engineering

Xi'an Jiaotong University

Research output: Contribution to journal › Article › peer-review

71 Scopus citations

Abstract

The course of the partial and total blockage of a channel in the IAEA 10 MW MTR pool type research reactor core (IAEA-TECDOC-233, 1980. IAEA Research Reactor Core Conversion from the use of high-enriched uranium to the use of low enriched uranium fuels Guidebook.) without scram is investigated. The analysis is performed with the best estimate code RELAP5/MOD3.3. The interaction of the obstructed channel and its adjacent channels has been taken account of. Results indicated that even when the flow channel has been totally blocked, there is still no boiling occurrence, and the fuel temperature is low enough to maintain its integrity. This work indicates that the consideration of the conjugate heat transfer in the obstructed channel during this transient is very important.

Original language	English
Pages (from-to)	45-50
Number of pages	6
Journal	Nuclear Engineering and Design
Volume	239
Issue number	1
DOIs	https://doi.org/10.1016/j.nucengdes.2008.06.016
State	Published - Jan 2009

Access to Document

10.1016/j.nucengdes.2008.06.016

Cite this

@article{04a96f717bd24391823e487bc9d536e4,

title = "Flow blockage analysis of a channel in a typical material test reactor core",

abstract = "The course of the partial and total blockage of a channel in the IAEA 10 MW MTR pool type research reactor core (IAEA-TECDOC-233, 1980. IAEA Research Reactor Core Conversion from the use of high-enriched uranium to the use of low enriched uranium fuels Guidebook.) without scram is investigated. The analysis is performed with the best estimate code RELAP5/MOD3.3. The interaction of the obstructed channel and its adjacent channels has been taken account of. Results indicated that even when the flow channel has been totally blocked, there is still no boiling occurrence, and the fuel temperature is low enough to maintain its integrity. This work indicates that the consideration of the conjugate heat transfer in the obstructed channel during this transient is very important.",

author = "Qing Lu and Suizheng Qiu and Su, \{G. H.\}",

year = "2009",

month = jan,

doi = "10.1016/j.nucengdes.2008.06.016",

language = "英语",

volume = "239",

pages = "45--50",

journal = "Nuclear Engineering and Design",

issn = "0029-5493",

publisher = "Elsevier B.V.",

number = "1",

}

TY - JOUR

T1 - Flow blockage analysis of a channel in a typical material test reactor core

AU - Lu, Qing

AU - Qiu, Suizheng

AU - Su, G. H.

PY - 2009/1

Y1 - 2009/1

N2 - The course of the partial and total blockage of a channel in the IAEA 10 MW MTR pool type research reactor core (IAEA-TECDOC-233, 1980. IAEA Research Reactor Core Conversion from the use of high-enriched uranium to the use of low enriched uranium fuels Guidebook.) without scram is investigated. The analysis is performed with the best estimate code RELAP5/MOD3.3. The interaction of the obstructed channel and its adjacent channels has been taken account of. Results indicated that even when the flow channel has been totally blocked, there is still no boiling occurrence, and the fuel temperature is low enough to maintain its integrity. This work indicates that the consideration of the conjugate heat transfer in the obstructed channel during this transient is very important.

AB - The course of the partial and total blockage of a channel in the IAEA 10 MW MTR pool type research reactor core (IAEA-TECDOC-233, 1980. IAEA Research Reactor Core Conversion from the use of high-enriched uranium to the use of low enriched uranium fuels Guidebook.) without scram is investigated. The analysis is performed with the best estimate code RELAP5/MOD3.3. The interaction of the obstructed channel and its adjacent channels has been taken account of. Results indicated that even when the flow channel has been totally blocked, there is still no boiling occurrence, and the fuel temperature is low enough to maintain its integrity. This work indicates that the consideration of the conjugate heat transfer in the obstructed channel during this transient is very important.

UR - https://www.scopus.com/pages/publications/57649100336

U2 - 10.1016/j.nucengdes.2008.06.016

DO - 10.1016/j.nucengdes.2008.06.016

M3 - 文章

AN - SCOPUS:57649100336

SN - 0029-5493

VL - 239

SP - 45

EP - 50

JO - Nuclear Engineering and Design

JF - Nuclear Engineering and Design

IS - 1

ER -

Flow blockage analysis of a channel in a typical material test reactor core

Abstract

Access to Document

Other files and links

Fingerprint

Cite this