RAMONA-MB neutron kinetics features and BWR rod-drop analysis
- Siemens Power Corporation, Richland, WA (United States)
A control blade drop accident in a boiling water reactor (BWR) causes an extremely high local power peaking. A three-dimensional simulation of this accident requires an accurate description of spatial phenomena integrated over a short time. For an actual reactor core design, a realistic analysis of such an event should be based on an accurate steady-state initialization in terms of Doppler and steam void history effect and a nonequilibrium thermal-hydraulics model to account for a very localized steam void generation. A combination of an advanced BWR core simulator such as MICROBURN-B and a proven system transient model such as RAMONA-3B satisfies this requirement for realistic analysis. The purpose of this paper is to present two distinct features and results of the kinetics extension of MICROBURN-B as implemented in the transient code RAMONA-MB.
- OSTI ID:
- 411653
- Report Number(s):
- CONF-951006-; ISSN 0003-018X; TRN: 97:000902
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 73; Conference: Winter meeting of the American Nuclear Society (ANS), San Francisco, CA (United States), 29 Oct - 1 Nov 1995; Other Information: PBD: 1995
- Country of Publication:
- United States
- Language:
- English
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