TY - GEN
T1 - Modeling digital control systems in TRACE
AU - Edwards, Robert M.
AU - Shaffer, Roman A.
AU - Arndt, Steven A.
PY - 2006
Y1 - 2006
N2 - The US Nuclear Regulatory Commission (NRC) has developed a number of thermal hydraulic safety analysis codes that are used to predict nuclear reactor and plant systems behavior under normal, accident, and severe accident conditions for current and advanced reactors. These codes supports NRC's assessment of continued safety of operating reactors, as well as anticipation of new safety issues and accident phenomena in nuclear plants, including advanced reactors. The current thermal hydraulic safety code of choice for the NRC is the TRAC RELAP Enhanced Computational Engine (TRACE). This safety analysis code has evolved to contain function block programming suitable for modeling analog control components. Until now, there has been no analytical model to study the response of digital control and safety systems for safety analysis in TRACE. New plant construction will be completely digital in the protection and control systems and existing plants are undergoing upgrades to replace analog components with digital systems. For upgrades to existing plants, NRC will review licensee analysis of any updates to current chapter 15 accident analyses, needed to support license amendment requests. For accident analysis of new plants and upgrades to existing plants that include digital components these analysis need to include the effects of digital components on the progress of the accidents in the analyses. This paper will present an approach to incorporate the digital components in the analysis.
AB - The US Nuclear Regulatory Commission (NRC) has developed a number of thermal hydraulic safety analysis codes that are used to predict nuclear reactor and plant systems behavior under normal, accident, and severe accident conditions for current and advanced reactors. These codes supports NRC's assessment of continued safety of operating reactors, as well as anticipation of new safety issues and accident phenomena in nuclear plants, including advanced reactors. The current thermal hydraulic safety code of choice for the NRC is the TRAC RELAP Enhanced Computational Engine (TRACE). This safety analysis code has evolved to contain function block programming suitable for modeling analog control components. Until now, there has been no analytical model to study the response of digital control and safety systems for safety analysis in TRACE. New plant construction will be completely digital in the protection and control systems and existing plants are undergoing upgrades to replace analog components with digital systems. For upgrades to existing plants, NRC will review licensee analysis of any updates to current chapter 15 accident analyses, needed to support license amendment requests. For accident analysis of new plants and upgrades to existing plants that include digital components these analysis need to include the effects of digital components on the progress of the accidents in the analyses. This paper will present an approach to incorporate the digital components in the analysis.
UR - http://www.scopus.com/inward/record.url?scp=34047095484&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:34047095484
SN - 0894480510
SN - 9780894480515
T3 - 5th International Topical Meeting on Nuclear Plant Instrumentation Controls, and Human Machine Interface Technology (NPIC and HMIT 2006)
SP - 1340
EP - 1351
BT - 5th International Topical Meeting on Nuclear Plant Instrumentation Controls, and Human Machine Interface Technology (NPIC and HMIT 2006)
T2 - 5th International Topical Meeting on Nuclear Plant Instrumentation Controls, and Human Machine Interface Technology (NPIC and HMIT 2006)
Y2 - 12 November 2006 through 16 November 2006
ER -