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

Conference · Mon Jul 01 00:00:00 EDT 1996

OSTI ID:250968

Ivanov, K N; Macian, R; Baratta, A J ^[1]; Irani, A; Folsom, J W; Trikouros, N G

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1. Pennsylvania State Univ., University Park, PA (United States)

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 1D 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.

• OSTI ID: 250968
• Report Number(s): CONF-960306--; ISBN 0-7918-1226-X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
COMPARATIVE EVALUATIONS
COMPUTERIZED SIMULATION
CONTROL ELEMENTS
POSITIONING
REACTOR ACCIDENTS
REACTOR CORES
REACTOR KINETICS
THREE MILE ISLAND-1 REACTOR