Main-steam-line-break analysis of TMI-1 using RETRAN-3D

Citation
Ce. Peterson et al., Main-steam-line-break analysis of TMI-1 using RETRAN-3D, NUCL TECH, 128(2), 1999, pp. 233-244
Citations number
7
Categorie Soggetti
Nuclear Emgineering
Journal title
NUCLEAR TECHNOLOGY
ISSN journal
00295450 → ACNP
Volume
128
Issue
2
Year of publication
1999
Pages
233 - 244
Database
ISI
SICI code
0029-5450(199911)128:2<233:MAOTUR>2.0.ZU;2-6
Abstract
A main-steam-line-break accident analysis for Three Mile Island Unit 1 is p erformed with point kinetics and three-dimensional kinetics with RETRAN-3D MOD002. These analyses were performed to demonstrate differences in results that can be expected due to different reactor kinetics models. To illustra te the difference in kinetics models, the RETRAN-3D models used for both an alyses were the same with the exception of the reactor core modeling. The k ey assumptions and methods used to model loop mixing are described. The point-kinetics analysis demonstrates a significant return-to-power foll owing the reactor trip while the three-dimensional kinetics case does not. This study shows that three-dimensional core transient modeling provides ma rgin to recriticality over a point-kinetics approach. Such margin is desira ble to allow for power uprate and extended refueling cycles.