PWR reactivity insertion accident methodology based on TRAC-PF1/NEM

Kostadin N. Ivanov; Justin K. Watson; Tara M. Beam; Anthony J. Baratta; Adi Irani; Nick Trikouros

PWR reactivity insertion accident methodology based on TRAC-PF1/NEM

Kostadin N. Ivanov
, Justin K. Watson
, Tara M. Beam
, Anthony J. Baratta
, Adi Irani
, Nick Trikouros

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

Abstract

A PWR Reactivity Insertion Accidents (RIA) analysis capability, based on the three-dimensional coupled thermal-hydraulic/neutronics code TRAC-PF1/NEM, has been developed. Several verification and validation studies were conducted showing that TRAC-PF1/NEM is qualified for RIA applications. The applications of TRAC-PF1/NEM to Rod Ejection Accident and the Main Steam Line Break transient analyses to upgrade the power of the TMI-1 NPP were also conducted. In these applications, TRAC-PF1/NEM was used with the Studsvik of America CASMO-3/SIMULATE-3 code package.

Original language	English (US)
Pages	183-184
Number of pages	2
State	Published - 1997
Event	Proceedings of the 1997 5th International Conference on Nuclear Engineering, ICONE5 - Nice, Fr Duration: May 25 1997 → May 29 1997

Other

Other	Proceedings of the 1997 5th International Conference on Nuclear Engineering, ICONE5
City	Nice, Fr
Period	5/25/97 → 5/29/97

All Science Journal Classification (ASJC) codes

Nuclear Energy and Engineering

Cite this

@conference{1a980740db7e4c4c9d6cca1da701bce2,

title = "PWR reactivity insertion accident methodology based on TRAC-PF1/NEM",

abstract = "A PWR Reactivity Insertion Accidents (RIA) analysis capability, based on the three-dimensional coupled thermal-hydraulic/neutronics code TRAC-PF1/NEM, has been developed. Several verification and validation studies were conducted showing that TRAC-PF1/NEM is qualified for RIA applications. The applications of TRAC-PF1/NEM to Rod Ejection Accident and the Main Steam Line Break transient analyses to upgrade the power of the TMI-1 NPP were also conducted. In these applications, TRAC-PF1/NEM was used with the Studsvik of America CASMO-3/SIMULATE-3 code package.",

author = "Ivanov, \{Kostadin N.\} and Watson, \{Justin K.\} and Beam, \{Tara M.\} and Baratta, \{Anthony J.\} and Adi Irani and Nick Trikouros",

year = "1997",

language = "English (US)",

pages = "183--184",

note = "Proceedings of the 1997 5th International Conference on Nuclear Engineering, ICONE5 ; Conference date: 25-05-1997 Through 29-05-1997",

}

TY - CONF

T1 - PWR reactivity insertion accident methodology based on TRAC-PF1/NEM

AU - Ivanov, Kostadin N.

AU - Watson, Justin K.

AU - Beam, Tara M.

AU - Baratta, Anthony J.

AU - Irani, Adi

AU - Trikouros, Nick

PY - 1997

Y1 - 1997

N2 - A PWR Reactivity Insertion Accidents (RIA) analysis capability, based on the three-dimensional coupled thermal-hydraulic/neutronics code TRAC-PF1/NEM, has been developed. Several verification and validation studies were conducted showing that TRAC-PF1/NEM is qualified for RIA applications. The applications of TRAC-PF1/NEM to Rod Ejection Accident and the Main Steam Line Break transient analyses to upgrade the power of the TMI-1 NPP were also conducted. In these applications, TRAC-PF1/NEM was used with the Studsvik of America CASMO-3/SIMULATE-3 code package.

AB - A PWR Reactivity Insertion Accidents (RIA) analysis capability, based on the three-dimensional coupled thermal-hydraulic/neutronics code TRAC-PF1/NEM, has been developed. Several verification and validation studies were conducted showing that TRAC-PF1/NEM is qualified for RIA applications. The applications of TRAC-PF1/NEM to Rod Ejection Accident and the Main Steam Line Break transient analyses to upgrade the power of the TMI-1 NPP were also conducted. In these applications, TRAC-PF1/NEM was used with the Studsvik of America CASMO-3/SIMULATE-3 code package.

UR - https://www.scopus.com/pages/publications/0030701014

UR - https://www.scopus.com/pages/publications/0030701014#tab=citedBy

M3 - Paper

AN - SCOPUS:0030701014

SP - 183

EP - 184

T2 - Proceedings of the 1997 5th International Conference on Nuclear Engineering, ICONE5

Y2 - 25 May 1997 through 29 May 1997

ER -

PWR reactivity insertion accident methodology based on TRAC-PF1/NEM

Abstract

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All Science Journal Classification (ASJC) codes

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