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Title: The Evaluation of Steam Generator Level Measurement Model for OPR1000 Using RETRAN-3D

Steam generator level measurement is important factor for plant transient analyses using best estimate thermal hydraulic computer codes since the value of steam generator level is used for steam generator level control system and plant protection system. Because steam generator is in the saturation condition which includes steam and liquid together and is the place that heat exchange occurs from primary side to secondary side, computer codes are hard to calculate steam generator level realistically without appropriate level measurement model. In this paper, we prepare the steam generator models using RETRAN-3D that include geometry models, full range feedwater control system and five types of steam generator level measurement model. Five types of steam generator level measurement model consist of level measurement model using elevation difference in downcomer, 1D level measurement model using fluid mass, 1D level measurement model using fluid volume, 2D level measurement model using power and fluid mass, and 2D level measurement model using power and fluid volume. And we perform the evaluation of the capability of each steam generator level measurement model by simulating the real plant transient condition, the title is 'Reactor Trip by The Failure of The Deaerator Level Control Card of Ulchin Unit 3'.more » The comparison results between real plant data and RETRAN-3D analyses for each steam generator level measurement model show that 2D level measurement model using power and fluid mass or fluid volume has more realistic prediction capability compared with other level measurement models. (authors)« less
Authors:
; ;  [1] ;  [2]
  1. FNC Technology Co., SNU Research Park Innovation Center 516, San4-2, Bongchun-7 dong, Kwanak-Gu, Seoul (Korea, Republic of)
  2. KHNP Nuclear Environment Technology Institute, Munji-dong 103-16, Yusung-Gu, Daejeon (Korea, Republic of)
Publication Date:
OSTI Identifier:
21016409
Resource Type:
Conference
Resource Relation:
Conference: 2006 International congress on advances in nuclear power plants - ICAPP'06, Reno - Nevada (United States), 4-8 Jun 2006; Other Information: Country of input: France; 7 refs; Related Information: In: Proceedings of the 2006 international congress on advances in nuclear power plants - ICAPP'06, 2734 pages.
Publisher:
American Nuclear Society - ANS, La Grange Park (United States)
Research Org:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; COMPARATIVE EVALUATIONS; COMPUTER CODES; CONTROL; CONTROL SYSTEMS; FAILURES; FEEDWATER; FORECASTING; GEOMETRY; HEAT; LEVELS; LIQUIDS; SAFETY; STEAM GENERATORS; THERMAL HYDRAULICS; TRANSIENTS