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Author Moon, H.
Source United States Department of Energy Office of Scientific and Technical Information
Content type Text
Language English
Subject Keyword NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS ♦ NUCLEAR REACTOR TECHNOLOGY ♦ MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS ♦ BWR TYPE REACTORS ♦ ROD DROP ACCIDENTS ♦ R CODES ♦ HYDRAULICS ♦ NODAL EXPANSION METHOD ♦ MATHEMATICAL MODELS
Abstract 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.
ISSN 0003018X
Educational Use Research
Learning Resource Type Article
Publisher Date 1995-12-31
Publisher Place United States
Journal Transactions of the American Nuclear Society
Volume Number 73
Technical Publication No. CONF-951006-


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