Experimental study on 1/28 scaled NGNP HTGR reactor building test facility response to depressurization event

Se Ro Yang; Ethan Kappes; Thien Nguyen; Rodolfo Vaghetto; Yassin Hassan

doi:10.1016/j.anucene.2017.12.023

Experimental study on 1/28 scaled NGNP HTGR reactor building test facility response to depressurization event

Se Ro Yang, Ethan Kappes, Thien Nguyen, Rodolfo Vaghetto, Yassin Hassan

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

16 Scopus citations

Abstract

The analysis and understanding of air ingress events are an important aspect of the design of high-temperature gas-cooled reactor (HTGR) accident scenarios. These include depressurized loss of forced cooling (D-LOFC) events that allow for the possibility of air ingress into the reactor pressure vessel as a result of a break in the helium pressure boundary, which can ultimately result in oxidation of the fuel elements and other nuclear-grade graphite components. To characterize air ingress into the vented low-pressure containment of the next generation nuclear plant HTGR during hypothetical moderate-sized D-LOFC break accidents experimentally, a 1/28 scaled simplified reactor building model was established. A non-dimensional similarity approach was employed for scaling of the experimental facility. Three experiments were designed and conducted to study the dynamic response to the accident scenario. The experimental results suggest an increment in the flow area of the check valve between the reactor cavity (CV1) and steam generator cavity (CV3). Furthermore, qualitative analysis was conducted on the experimental data.

Original language	English
Pages (from-to)	154-164
Number of pages	11
Journal	Annals of Nuclear Energy
Volume	114
DOIs	https://doi.org/10.1016/j.anucene.2017.12.023
State	Published - Apr 2018
Externally published	Yes

Funding

This study is based on work supported by the Department of Energy [ National Nuclear Security Administration ] under Award Number [ DE-NE0008324 ], in cooperation with AREVA Federal Service LLC (AFS), the Ultra Safe Nuclear Corporation ( USNC ), and AREVA Inc . This report was prepared as an account of work sponsored by an agency of the United States Government . Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

Keywords

Air-ingress
Depressurization
HTGR
LOFC
NGNP
Oxygen concentration
Pressure response
Reactor building
VLPC

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10.1016/j.anucene.2017.12.023

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title = "Experimental study on 1/28 scaled NGNP HTGR reactor building test facility response to depressurization event",

abstract = "The analysis and understanding of air ingress events are an important aspect of the design of high-temperature gas-cooled reactor (HTGR) accident scenarios. These include depressurized loss of forced cooling (D-LOFC) events that allow for the possibility of air ingress into the reactor pressure vessel as a result of a break in the helium pressure boundary, which can ultimately result in oxidation of the fuel elements and other nuclear-grade graphite components. To characterize air ingress into the vented low-pressure containment of the next generation nuclear plant HTGR during hypothetical moderate-sized D-LOFC break accidents experimentally, a 1/28 scaled simplified reactor building model was established. A non-dimensional similarity approach was employed for scaling of the experimental facility. Three experiments were designed and conducted to study the dynamic response to the accident scenario. The experimental results suggest an increment in the flow area of the check valve between the reactor cavity (CV1) and steam generator cavity (CV3). Furthermore, qualitative analysis was conducted on the experimental data.",

keywords = "Air-ingress, Depressurization, HTGR, LOFC, NGNP, Oxygen concentration, Pressure response, Reactor building, VLPC",

author = "Yang, {Se Ro} and Ethan Kappes and Thien Nguyen and Rodolfo Vaghetto and Yassin Hassan",

note = "Publisher Copyright: {\textcopyright} 2017",

year = "2018",

month = apr,

doi = "10.1016/j.anucene.2017.12.023",

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AU - Yang, Se Ro

AU - Kappes, Ethan

AU - Nguyen, Thien

AU - Vaghetto, Rodolfo

AU - Hassan, Yassin

PY - 2018/4

Y1 - 2018/4

N2 - The analysis and understanding of air ingress events are an important aspect of the design of high-temperature gas-cooled reactor (HTGR) accident scenarios. These include depressurized loss of forced cooling (D-LOFC) events that allow for the possibility of air ingress into the reactor pressure vessel as a result of a break in the helium pressure boundary, which can ultimately result in oxidation of the fuel elements and other nuclear-grade graphite components. To characterize air ingress into the vented low-pressure containment of the next generation nuclear plant HTGR during hypothetical moderate-sized D-LOFC break accidents experimentally, a 1/28 scaled simplified reactor building model was established. A non-dimensional similarity approach was employed for scaling of the experimental facility. Three experiments were designed and conducted to study the dynamic response to the accident scenario. The experimental results suggest an increment in the flow area of the check valve between the reactor cavity (CV1) and steam generator cavity (CV3). Furthermore, qualitative analysis was conducted on the experimental data.

AB - The analysis and understanding of air ingress events are an important aspect of the design of high-temperature gas-cooled reactor (HTGR) accident scenarios. These include depressurized loss of forced cooling (D-LOFC) events that allow for the possibility of air ingress into the reactor pressure vessel as a result of a break in the helium pressure boundary, which can ultimately result in oxidation of the fuel elements and other nuclear-grade graphite components. To characterize air ingress into the vented low-pressure containment of the next generation nuclear plant HTGR during hypothetical moderate-sized D-LOFC break accidents experimentally, a 1/28 scaled simplified reactor building model was established. A non-dimensional similarity approach was employed for scaling of the experimental facility. Three experiments were designed and conducted to study the dynamic response to the accident scenario. The experimental results suggest an increment in the flow area of the check valve between the reactor cavity (CV1) and steam generator cavity (CV3). Furthermore, qualitative analysis was conducted on the experimental data.

KW - Air-ingress

KW - Depressurization

KW - HTGR

KW - LOFC

KW - NGNP

KW - Oxygen concentration

KW - Pressure response

KW - Reactor building

KW - VLPC

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DO - 10.1016/j.anucene.2017.12.023

M3 - Article

AN - SCOPUS:85037971504

SN - 0306-4549

VL - 114

SP - 154

EP - 164

JO - Annals of Nuclear Energy

JF - Annals of Nuclear Energy

ER -

Experimental study on 1/28 scaled NGNP HTGR reactor building test facility response to depressurization event

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Keywords

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