TMI MSLB analysis using TRAC-PF1 coupled with three-dimensional kinetics

K. N. Ivanov, R. Macian, A. J. Baratta, A. Irani, J. W. Folsom, N. G. Trikouros

Research output: Chapter in Book/Report/Conference proceedingChapterpeer-review

7 Scopus citations

Abstract

The Main Steam Line Break (MSLB) accident in a pressurized water reactor is characterized by significant space-time effects in the core caused by asymmetric cooling and assumed stuck-out rod during reactor trip. Simulation of transients involving asymmetric core power peaking requires evaluation of the core response from a multi-dimensional perspective. These effects are analyzed in this paper for TMI Cycle 10 using the TRAC-PF1/NEM computer code. The TRAC-PF1/NEM methodology utilizes a closely coupled transient three-dimensional thermal-hydraulics vessel and three-dimensional neutronics core models supplemented by 1-D simulation of the remainder of the reactor coolant system. A comparison of the 3-D kinetics results to a compatible point kinetics prediction is also performed.

Original languageEnglish
Title of host publicationProceedings of the ASME/JSME International Conference on Nuclear Engineering, ICONE
EditorsA.S. Rao, R.B. Duffey, D. Elias
Pages33-40
Number of pages8
StatePublished - 1996
Externally publishedYes
EventProceedings of the 1996 4th ASME/JSME International Conference on Nuclear Engineering, ICONE-4. Part 4 (of 5) - New Orleans, LA, USA
Duration: 10 Mar 199614 Mar 1996

Publication series

NameProceedings of the ASME/JSME International Conference on Nuclear Engineering, ICONE
Volume3

Conference

ConferenceProceedings of the 1996 4th ASME/JSME International Conference on Nuclear Engineering, ICONE-4. Part 4 (of 5)
CityNew Orleans, LA, USA
Period10/03/9614/03/96

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