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Nuclear Software Engineering ( related papers )

Software Verification & Validation

Verification & Validation (V&V)

  • •Verification: Comparison of the Stage-by-Stage Software Development to Determine that There is a Faithful Translation of One Stage into the Next Stage
  • •Validation: Test and Evaluation of the Integrated Computer System to Ensure Compliance with the Functional, Performance and Interface Requirements

Application of Formal Method to I&C Software System

  • •Formal Specification
  • •Formal Analysis

The V&V Environment Construction for NPP Software System

Integrated V&V Tool for Nuclear Fields

•Approach for Easy Inspection and Effective Use of Formal Method
•Automated Traceability Analysis Supporting
•Software Configuration Management Supporting

Digital Upgrade of I&C System

•Development of Digitalized I&C System with Advanced Algorithm
•Analysis of I&C System Document and Software

Integrated Environment for S/W Development and V&V

NuSISRT

•Nuclear Software Inspection Supporting and Requirement Traceability Tool
•Supports not only concept phase but also whole S/W life cycle based on documents
•Major features

  • •Inspection View
  • ◦Supports systematic inspection with checklist
  • ◦An extraction function of requirements
  • •Traceability View
  • ◦Links between source and destination documents
  • ◦Supports similarity calculation function
  • •Structure View
  • ◦Structure analysis of a system
  • ◦Interface with NuSRS
NuSRS

•Nuclear requirment formal specification and verification tool
•Supports software requirement phase
•Major features

  • •Function Overview Diagram (FOD)
  • ◦A knid of Data Flow Diagram
  • ◦Describes the relationship btw. Input and Output
  • •Structured Decision Table (SDT)
  • ◦A kind of Condition/Action table
  • ◦Tabular notation
  • •Finite State Machine (FSM)
  • ◦State-based behavior of a system
  • •Timed Transition System (TTS)
  • ◦Time-related behavior of a system
  • •Formal verification using PVS and/or SMV
NuSDS

•Nuclear design specification and verification tool
•Supports software design phase
•Major features

  • •Database design
  • ◦It is a basis of whole system S/W design.
  • •S/W architecture design
  • ◦S/W module decomposition for PLC programming
  • •S/W behavior design
  • ◦System's behaviors will be described by FBD-style specification
  • •H/W configuration design
  • ◦Layout diagram for PLC H/W configuration
NuSCM

•Nuclear Software Configuration Management tool
•Supports whole S/W lifecycle based on Cis (Configuration items)
•Major features

  • •Project centered SCM supporting
  • ◦Reflects upon present corporations' projects
  • •Change request form in nuclear fields supporting
  • ◦Supports change approval processes
  • •Source code management supporting
  • ◦Supports workspace (client file system designed for efficient source code version control)

Development of a Safety-Critical V&V Tool (NuSEE)

Related Papers

International Journal Papers

  • Han Seong Son and Poong Hyun Seong. "Quantitative Evaluation of Safety-Critical Software at the Early Development Stage : An Interposing Logic System Software Example, Reliability Engineering and System Safety, Vol. 50, 1995
  • Jung Soo Koh, Poong Hyun Seong, Han Seong Son, "Formal Safety Analysis for PLC Software-Based Safety Critical System Using Z", ANS Transaction, Vol. 70, 314 -315, 1997
  • Han Seong Son, Poong Hyun Seong, "Mathematical Verification of an NPP Protection System Function with Combined CPN and PVS", Transactions of the American Nuclear Society, vol.79, 247-249, 1998
  • Han Seong Son and Poong H. Seong, "A Quality control Method for Nuclear Instrumentation and Control systems based on Software Safety Prediction", IEEE Trans. on Nuclear Science, Accepted, 2000
  • Seo Ryong Koo, Poong Hyun Seong and Han Seong Son, "Development of Digital Online Active Test Plant Protection System". Transactions of the American Nuclear Society, Vol. 85 P. 399-400, 2001, 11
  • Jung Hwan Lee and Poong Hyun Seong, "Development of a Safety Analysis Method for Requirements Based on Statechart Using Combined SCR and ISO tables", Transactions of the American Nuclear Society, Vol 85, P.398-399, 2001, 11

International Conference Papers

  • Han Seong Son, Poong H. Seong, "Quantitative Estimations for Safety-critical Software",
    Technology, Methods and Future, Philadelphia, 1995, 6
  • Han S. Son, Poong H. Seong, "Development of Software Test Case Generator for Nuclear Plant I&C System Software", The 1996 ANS International Topical Meeting on Nuclear I&C and Human-Machine Interface Technology, Pennsylvania, USA, 1996, 5
  • Han Seong Son and Poong Hyun Seong, ""A Software Evaluation Method Based on Fuzzy Colored Petri Nets"", FUZZ-IEEE '99, Seoul, Korea, 1999, 08
  • Seo Ryong Koo, Han Seong Son and Poong Hyun Seong, "A Method of Formal Requirement Analysis for NPP I&C Systems Based on Object-Oriented UML Modeling with Software Cost Reduction", International Topical Meeting on Nuclear Plant Instrumentation, Controls, and Human-Machine Interface Technologies (NPIC&HMIT 2000), Washington, DC, USA, 2000, 11
  • Han Seong Son and Poong Hyun Seong, "Safety Prediction for Basic Components of Safety-Critical Software Based on Static Testing", International Youth Nuclear Congress 2000, Slovakia / Bratislava, 2000, 4

Domestic Journal Papers

  • Han Seong Son, Poong Hyun Seong, "A Quantitative Evaluation of Chemical and Volume control System Design Simplification", Proceeding of the Korea Nuclear Society Autumn Meeting , Vol. 27, No. 5, 1995, 10
  • Seo Ryong Koo, Han Seong Son, Poong Hyun Seong, "Mathematical Verification of a Nuclear Power Plant Protection System Function with Combined CPN and PVS", Journal of the Korea Nuclear Society Spring Meeting, P. 157 - 171, 1999, 4
  • Han Seong Son, Poong Hyun Seong, "Critical 소프트웨어의 신뢰도 예측에 관한 연구", Journal of the Korea Nuclear Society Spring Meeting , P. 175 - 180, 1994, 5
  • Han Seong Son, Poong Hyun Seong, "Fuzzy Colored Petri Nets and Their Application to Efficient Design and V&V of Fuzzy Logic Controllers", Journal of the Korea Nuclear Society Autumn Meeting, Seoul, Korea, P. 91 - 91, 1998, 10
  • Seo Ryong Koo, Han Seong Son, Poong Hyun Seong, "Mathematical Verification of A Nuclear Power Plant Protection System Function with Combined CPN and PVS", Journal of the Korea Nuclear Society Spring Meeting, Soowon, Korea, P. 315 - 320, 1998, 5

Domestic Conference Papers

  • Seo Ryong Koo and Poong Hyun Seong, "A Method of Formal Requirements Analysis for NPP I&C systems Based on Object-Oriented Visual Modeling with SCR", Proceeding of the Korea Nuclear Society Spring Meeting , Seoul, Korea, 1999, 10
  • Han Seong Son, Poong Hyun Seong, "SIS-RT: An Integrated Software Inspection Support and Requirement Traceability Tool", Proceeding of the Korea Nuclear Society Spring Meeting, Taejoun, Korea, 2000, 10
  • Seo Ryong Koo, Han Seong Son, Poong Hyun Seong, Hyung Jin Sim, "Development of Digital Online Active Test Plant Protection System (DOAT-PPS) for PWR",Proceeding of the Korea Nuclear Society Spring Meeting, Taejoun, Korea, 2000, 10
  • Seo Ryong Koo, Han Seong Son, Poong Hyun Seong, "원전 계측제어계통 소프트웨어 확인검증을 위한 지능형 통합환경 설계", Proceeding of the Korea Nuclear Society Spring Meeting, Cheju, Korea, 2001, 5
  • Jung Hoan Lee, Seo Ryong Koo, Han Seong Son, Poong Hyun Seong, "Development of Software Safety Analysis Method for Nuclear Power Plant I&C Systems in Requirement Specification Based on Statechart and SCR",Proceeding of the Korea Nuclear Society Spring Meeting, Cheju, Korea, 2001, 5