The TMI MSLB analysis using TRAC-PF1 coupled with three-dimensional kinetics
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:411678
- Pennsylvania State Univ., University Park, PA (United States)
- GPU Nuclear Corporation, Middletown, 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. These effects are analyzed in this paper for Three Mile Island (TMI) cycle 10, using closely coupled transient three-dimensional thermal-hydraulic vessel and neutronics core models supplemented by one-dimensional simulation of the remainder of the reactor coolant system. Also, a comparison of the three-dimensional kinetics results to a compatible point kinetics prediction is performed.
- OSTI ID:
- 411678
- Report Number(s):
- CONF-951006--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 73; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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