Application of RELAP5/MOD3.1 to ATWS Analysis of Control Rod Withdrawal From 1% Power Level (NUREG/IA-0180)
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Publication Information
Date Published: June 2000
Prepared by:
H. Kantee
Fortum Engineering Ltd.
P.O. Box 10
00048 Fortum
FINLAND
Prepared as part of:
The Code Application and Maintenance Program (CAMP)
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
Availability Notice
Abstract
The RELAP5/MOD3.1 computer code has been applied in the analysis of a regulating control rod group withdrawal from 1 % power level. The analysis has been carried out as an Anticipated Transient Without Scram (ATWS) event.
The analysis is related to an extensive inherent boron dilution study which was performed to Loviisa Nuclear Power Plant (NPP) in the mid 1990's. The main goal of the analysis was to study if during the accident so called boiling-condensing mode develops and thereafter a water plug with low boron concentration is formed in the cold leg loop seal.
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