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http://dx.doi.org/10.14248/JKOSSE.2018.14.2.024

Development of Simplified DNBR Calculation Algorithm using Model-Based Systems Engineering Methodology  

Awad, Ibrahim Fathy (KEPCO International Nuclear Graduate School)
Jung, Jae Cheon (KEPCO International Nuclear Graduate School)
Publication Information
Journal of the Korean Society of Systems Engineering / v.14, no.2, 2018 , pp. 24-32 More about this Journal
Abstract
System Complexity one of the most common cause failure of the projects, it leads to a lack of understanding about the functions of the system. Hence, the model is developed for communication and furthermore modeling help analysis, design, and understanding of the system. On the other hand, the text-based specification is useful and easy to develop but is difficult to visualize the physical composition, structure, and behaviour or data exchange of the system. Therefore, it is necessary to transform system description into a diagram which clearly depicts the behaviour of the system as well as the interaction between components. According to the International Atomic Energy Agency (IAEA) Safety Glossary, The safety system is a system important to safety, provided to ensure the safe shutdown of the reactor or the residual heat removal from the reactor core, or to limit the consequences of anticipated operational occurrences and design basis accidents. Core Protection Calculator System (CPCS) in Advanced Power Reactor 1400 (APR 1400) Nuclear Power Plant is a safety critical system. CPCS was developed using systems engineering method focusing on Departure from Nuclear Boiling Ratio (DNBR) calculation. Due to the complexity of the system, many diagrams are needed to minimize the risk of ambiguities and lack of understanding. Using Model-Based Systems Engineering (MBSE) software for modeling the DNBR algorithm were used. These diagrams then serve as the baseline of the reverse engineering process and speeding up the development process. In addition, the use of MBSE ensures that any additional information obtained from auxiliary sources can then be input into the system model, ensuring data consistency.
Keywords
Advanced Power Reactor; Core Protection Calculator System; Departure from Nucleate Boiling Ratio; Model-based Systems Engineering; Local Power Density;
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  • Reference
1 Functional Design Requirements for a Core Protection Calculator System, 2006, KNF-KSNGEN-03026, Rev.03.
2 Design of Instrumentation and Control Systems for Nuclear Power Plants, 2016, IAEA, Specific Safety Guide, SSG-39.
3 Verification and Validation of Software Related to Nuclear Power Plant Instrumentation and Control, 1990, IAEA, Technical Reports Series, No. 384.
4 Verification and Validation of Software Related to Nuclear Power Plant Instrumentation and Control, 1990, IAEA, Technical Reports Series, No. 384.
5 Recommended Practice for Software Requirements Specifications, 1993, IEEE, 830.
6 Systems Engineering Handbook, Guide for system Life Cycle Process and Activities, 4'th edition, 2015, INCOSE-TP-2003-002-04.
7 NASA Systems Engineering Handbook, Rev1, National Aeronautics and Space Administration, NASA/SP-2007-6105.
8 Systems Design, Software Design Descriptions, 2009, IEEE, 1016.
9 Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category a functions, 2006, IEC, 60880.
10 Nuclear power plants - Enhanced functional analysis system technique for managing complex engineering projects, 2007, Sofia Tan, Missouri University of science and Technology, 4572.
11 Nuclear power plants - A prime for Model-Based Systems Engineering, Second Edition 2011, David Long and Zane Scott, Vitech, ISBN 978-1-105-58810-5.
12 Reference document for the organization and conduct of Engineering Safety Review Services (ESRS) on software important to safety in nuclear power plants, 2000, IAEA, Services Series No. 6.
13 Business Modelling: UML vs. IDEF, 2000, Ovidiu S.Niran, ttp://www.cit.gu.edu.au/-noran.
14 IAEA SAFETY GLOSSARY, Terminology Used in Nuclear Safety and Radiation Protection, 2016.
15 Dependability Assessment of Software for Safety Instrumentation and Control Systems at Nuclear Power Plants, 2018, IAEA SERIES No. NP-T-3.27
16 Verification, Validation, Reviews, and Audits for Digital Computer Software Used In Safety Systems of Nuclear Power Plants, 2004, REGULATORY GUIDE 1.168, U.S. Nuclear Regulatory Commission (NRC).