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

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

Research output: Contribution to conferencePaper

2 Citations (Scopus)

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 languageEnglish (US)
Pages183-184
Number of pages2
StatePublished - Jan 1 1997
EventProceedings of the 1997 5th International Conference on Nuclear Engineering, ICONE5 - Nice, Fr
Duration: May 25 1997May 29 1997

Other

OtherProceedings of the 1997 5th International Conference on Nuclear Engineering, ICONE5
CityNice, Fr
Period5/25/975/29/97

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Accidents
Steam piping systems
Hydraulics
Hot Temperature

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

Cite this

Ivanov, K. N., Watson, J. K., Beam, T. M., Baratta, A. J., Irani, A., & Trikouros, N. (1997). PWR reactivity insertion accident methodology based on TRAC-PF1/NEM. 183-184. Paper presented at Proceedings of the 1997 5th International Conference on Nuclear Engineering, ICONE5, Nice, Fr, .
Ivanov, Kostadin N. ; Watson, Justin Kyle ; Beam, Tara M. ; Baratta, Anthony J. ; Irani, Adi ; Trikouros, Nick. / PWR reactivity insertion accident methodology based on TRAC-PF1/NEM. Paper presented at Proceedings of the 1997 5th International Conference on Nuclear Engineering, ICONE5, Nice, Fr, .2 p.
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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 Kyle} and Beam, {Tara M.} and Baratta, {Anthony J.} and Adi Irani and Nick Trikouros",
year = "1997",
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pages = "183--184",
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Ivanov, KN, Watson, JK, Beam, TM, Baratta, AJ, Irani, A & Trikouros, N 1997, 'PWR reactivity insertion accident methodology based on TRAC-PF1/NEM' Paper presented at Proceedings of the 1997 5th International Conference on Nuclear Engineering, ICONE5, Nice, Fr, 5/25/97 - 5/29/97, pp. 183-184.

PWR reactivity insertion accident methodology based on TRAC-PF1/NEM. / Ivanov, Kostadin N.; Watson, Justin Kyle; Beam, Tara M.; Baratta, Anthony J.; Irani, Adi; Trikouros, Nick.

1997. 183-184 Paper presented at Proceedings of the 1997 5th International Conference on Nuclear Engineering, ICONE5, Nice, Fr, .

Research output: Contribution to conferencePaper

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

AU - Ivanov, Kostadin N.

AU - Watson, Justin Kyle

AU - Beam, Tara M.

AU - Baratta, Anthony J.

AU - Irani, Adi

AU - Trikouros, Nick

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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.

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Ivanov KN, Watson JK, Beam TM, Baratta AJ, Irani A, Trikouros N. PWR reactivity insertion accident methodology based on TRAC-PF1/NEM. 1997. Paper presented at Proceedings of the 1997 5th International Conference on Nuclear Engineering, ICONE5, Nice, Fr, .