Investigation on the Benefits of Safety Margin Improvement in CANDU Nuclear Power Plant Using an FPGA-based Shutdown System
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[1] Jin Jiang,et al. Modeling and Simulation of a Candu Reactor for Control System Design and Analysis , 2009 .
[2] Ishtiaq Hussain Bokhari,et al. Analysis of loss of flow accident at Pakistan research reactor-1 , 2005 .
[3] César Torres-Huitzil,et al. An FPGA architecture for high speed edge and corner detection , 2000, Proceedings Fifth IEEE International Workshop on Computer Architectures for Machine Perception.
[4] John W. Lockwood,et al. A Modular System for FPGA-Based TCP Flow Processing in High-Speed Networks , 2004, FPL.
[5] Alessandro Petruzzi,et al. RELAP5 simulation of surge line break accident using combined and best estimate plus uncertainty approaches , 2009 .
[6] Anthony Salazar,et al. Radiation Test Results of the Virtex FPGA and ZBT SRAM for Space Based Reconfigurable Computing , 1999 .
[7] Bev Littlewood,et al. The problems of assessing software reliability ...When you really need to depend on it , 2000 .
[9] Dan Craigen,et al. Case study: Darlington nuclear generating station [software-driven shutdown systems] , 1994, IEEE Software.
[10] NTERNATIOf iROUP. Defence in Depth in Nuclear Safety INSAG-10 , 2003 .
[11] J. M. Cuttler,et al. Application of Semiconductor Logic Components in Reactor Safety and Regulating Systems , 1982, IEEE Transactions on Nuclear Science.
[12] Miodrag Bolic,et al. Digital gamma-ray spectroscopy based on FPGA technology , 2002 .
[13] O. Glöckler. Testing the dynamics of shutdown systems instrumentation in reactor trip measurements , 2003 .
[14] Nancy G Leveson,et al. Software safety: why, what, and how , 1986, CSUR.
[15] Kazuyuki Takeda,et al. OPENCORE NMR: open-source core modules for implementing an integrated FPGA-based NMR spectrometer. , 2008, Journal of magnetic resonance.
[16] B. N. Hanna,et al. CATHENA: A thermalhydraulic code for CANDU analysis , 1998 .
[17] Jin Jiang,et al. Potential improvement of CANDU NPP safety margins by shortening the response time of shutdown systems using FPGA based implementation , 2012 .
[18] R. Garello,et al. FPGA implementation of digital filters for nuclear detectors , 2009 .
[19] R. S. Rao,et al. Assessment methodology for confidence in safety margin for large break loss of coolant accident sequences , 2011 .
[20] Yan Lin,et al. Device and architecture concurrent optimization for FPGA transient soft error rate , 2007, ICCAD 2007.
[21] R. Chaouadi,et al. Improved safety margins for Belgian nuclear power plants by the application of the Master Curve approach to RPV surveillance materials , 2007 .
[22] Yu Hu,et al. Cross-layer optimized placement and routing for FPGA soft error mitigation , 2011, 2011 Design, Automation & Test in Europe.
[23] Louis M. Shotkin,et al. USE OF THE PROMPT-JUMP APPROXIMATION IN FAST-REACTOR KINETICS. , 1969 .
[24] Daniel Dupleac,et al. Severe accident development modeling and evaluation for CANDU , 2009 .
[25] Nasir Ahmad,et al. Reactivity feedback and control margins in natural uranium fueled and heavy water moderated nuclear research reactors , 2006 .
[27] Meng-Shiun Tsai,et al. Real-time NURBS interpolation using FPGA for high speed motion control , 2006, Comput. Aided Des..
[28] N.K. Trehan,et al. Nuclear power revival , 2003, 2003 IEEE Nuclear Science Symposium. Conference Record (IEEE Cat. No.03CH37515).
[29] Eric Lemoine,et al. Run time reconfiguration of FPGA for scanning genomic databases , 1995, Proceedings IEEE Symposium on FPGAs for Custom Computing Machines.
[30] Alan Wassyng,et al. Lessons Learned from a Successful Implementation of Formal Methods in an Industrial Project , 2003, FME.
[31] Yan Lin,et al. Device and architecture concurrent optimization for FPGA transient soft error rate , 2007, 2007 IEEE/ACM International Conference on Computer-Aided Design.
[32] Kenneth E. Batcher,et al. Minimizing Communication in the Bitonic Sort , 2000, IEEE Trans. Parallel Distributed Syst..
[33] An evaluation of the severe accident management strategies for CANDU-6 type plants , 2009 .
[34] David D. Wentzloff,et al. A scalable FPGA-based digitizing platform for radiation data acquisition , 2011 .
[35] Vaughn Betz,et al. Speed and area tradeoffs in cluster-based FPGA architectures , 2000, IEEE Trans. Very Large Scale Integr. Syst..
[36] H. Murakoshi,et al. An application of FPGA to high-speed programmable controller: development of the conversion program from SFC to Verilog , 1999, 1999 7th IEEE International Conference on Emerging Technologies and Factory Automation. Proceedings ETFA '99 (Cat. No.99TH8467).
[37] Y. Rao,et al. Thermal hydraulic analysis of the thorium-based advanced CANDU Reactor fuel channel , 2006 .
[38] Hoang Le-Huy,et al. An FPGA-based rapid prototyping platform for variable-speed drives , 2002, IEEE 2002 28th Annual Conference of the Industrial Electronics Society. IECON 02.
[39] Jin Jiang,et al. CANDU Reactor Space-Time Kinetic Model for Load Following Studies , 2011 .
[40] François M. Hemez,et al. Improved best estimate plus uncertainty methodology, including advanced validation concepts, to license evolving nuclear reactors , 2011 .
[41] Trevor A. York. Survey of field programmable logic devices , 1993, Microprocess. Microsystems.
[42] T. U. Bhatt,et al. Application of fuzzy logic control system for regulation of differential pressure in Liquid Zone Control System , 2009 .
[43] Void reactivity and pin power calculation for a CANDU cell using the SEU-43 fuel bundle , 2003 .
[44] P. J. Ingham,et al. LOCA assessment experiments in a full-elevation, CANDU-typical test facility , 1990 .
[45] Jin Jiang,et al. A Hardware-in-the-Loop Simulation Platform for the Verification and Validation of Safety Control Systems , 2011, IEEE Transactions on Nuclear Science.
[46] A. P. Muzumdar,et al. POWER REACTOR SAFETY COMPARISON – A LIMITED REVIEW , 2009 .
[47] Byung-Joo Min,et al. Moderator Analysis of Wolsong Units 2/3/4 for the 35% Reactor Inlet Header Break with a Loss of Emergency Core Cooling Injection , 2006 .
[48] E. Badreddin,et al. Dynamic safety margin principle and application in control of safety critical systems , 2004, Proceedings of the 2004 IEEE International Conference on Control Applications, 2004..
[49] Vaughn Betz,et al. FPGA routing architecture: segmentation and buffering to optimize speed and density , 1999, FPGA '99.
[50] R. Mendizabal,et al. Safety margins estimation method considering uncertainties within the risk- informed decision-making framework , 2006 .
[51] Lei Wang,et al. A modular FPGA-based ultrasonic array system for applications including non-destructive testing , 2008 .
[52] Michael John Sebastian Smith,et al. Application-specific integrated circuits , 1997 .
[53] Daniel Dupleac,et al. Generic CANDU 6 plant severe accident analysis employing SCAPSIM/RELAP5 code , 2009 .
[54] Simon Pang,et al. CANDU technology for Generation III+ and IV reactors , 2006 .
[55] Lu Ying-hua,et al. Design and implementation of high-speed real-time data acquisition .system based on FPGA , 2006 .
[56] Álvaro Hernández,et al. A DSP- and FPGA-Based Industrial Control With High-Speed Communication Interfaces for Grid Converters Applied to Distributed Power Generation Systems , 2009, IEEE Transactions on Industrial Electronics.
[57] Vyacheslav Kharchenko,et al. Reliability and availability analysis of FPGA-based Instrumentation and Control systems , 2011, 2011 11th International Conference The Experience of Designing and Application of CAD Systems in Microelectronics (CADSM).
[58] Shekhar Y. Borkar,et al. Electronics beyond nano-scale CMOS , 2006, 2006 43rd ACM/IEEE Design Automation Conference.
[59] James R. Armstrong,et al. VHDL Design Representation and Synthesis , 2000 .
[60] P. Pani,et al. GEMS: Underwater spectrometer for long-term radioactivity measurements , 2011 .
[61] Enrico Zio,et al. Safety margins confidence estimation for a passive residual heat removal system , 2010, Reliab. Eng. Syst. Saf..
[62] Shekhar Y. Borkar,et al. Designing reliable systems from unreliable components: the challenges of transistor variability and degradation , 2005, IEEE Micro.
[63] K. Ott,et al. Introductory Nuclear Reactor Dynamics , 1985 .
[64] Bo Wook Rhee,et al. A blind simulation of RD-14M small-break LOCA experiments using CATHENA code , 2011 .
[65] R. S. Gilbert. Digitial Computers in CANDU Safety Systems: Part II Implementation and Experience , 1983, IEEE Transactions on Nuclear Science.
[66] Hitoshi Ishii,et al. Development of a high speed imaging microscope and new software for nuclear track detector analysis , 2005 .
[67] Jonathan Rose,et al. Optimization of field-programmable gate array logic block architecture for speed , 1991, Proceedings of the IEEE 1991 Custom Integrated Circuits Conference.
[68] Robert Beauwens,et al. The improved prompt jump approximation , 2007 .
[69] A.M.C. Chan,et al. On the thermal analysis of pressure tube/calandria tube contact in CANDU reactors , 1987 .
[70] Yong Dou,et al. 64-bit floating-point FPGA matrix multiplication , 2005, FPGA '05.
[71] David W. Dilks,et al. Improved consideration of the margin of safety in total maximum daily load development , 2004 .
[72] Joseph G. Murray,et al. Developing Licensable FPGA-Based Safety Systems , 2010 .
[73] P. K. Joannou,et al. Ontario Hydro/AECL standards for software engineering deficiencies in existing standards that created their need , 1995, Proceedings of Software Engineering Standards Symposium.
[74] G. Horhoianu,et al. Candu type fuel behavior during rapid overpower transients , 1998 .
[75] Jin Jiang,et al. On the speed of response of an FPGA-based shutdown system in CANDU nuclear power plants , 2011 .
[76] Doddy Kastanya,et al. Regional overpower protection analysis for CANDU 6 reactors using ROVER-F code , 2010 .
[77] Bo Wook Rhee,et al. Development and validation of a CATHENA fuel channel model for a post-blowdown analysis of the high temperature thermal–chemical experiment CS28-1 , 2009 .
[78] Ron Bell,et al. Introduction to IEC 61508 , 2006 .
[79] J. Hammersley. SIMULATION AND THE MONTE CARLO METHOD , 1982 .
[80] Bev Littlewood,et al. The use of computers in safety-critical applications , 1998 .
[81] U Pulkkinen,et al. Licensing process for safety-critical software-based systems , 2000 .
[82] G. Bartholomé,et al. Activities in the field of plant life evaluation, life extension and plant improvement , 1991 .
[83] R. P. Martin,et al. Perspectives on the Application of Order-Statistics in Best-Estimate Plus Uncertainty Nuclear Safety Analysis , 2011 .
[84] E. Badreddin,et al. Application of model predictive control for fault tolerant system using dynamic safety margin , 2006, 2006 American Control Conference.
[85] Gord L. Brooks. A Short History of the CANDU Nuclear Power System , 2002 .
[86] J. Robertson. The CANDU Reactor System: An Appropriate Technology. , 1978, Science.
[87] Hangbok Choi. A fast-running fuel management program for a CANDU reactor , 2000 .
[88] Didier Demigny,et al. How to use high speed reconfigurable FPGA for real time image processing? , 2000, Proceedings Fifth IEEE International Workshop on Computer Architectures for Machine Perception.
[89] N. M. Ichiyen,et al. Digital Computers in Candu Safety Systems Part I History and Concepts , 1983, IEEE Transactions on Nuclear Science.
[90] STEPHEN BROWN,et al. Minimizing FPGA Interconnect Delays , 1996, IEEE Des. Test Comput..
[91] Daniel Dupleac,et al. SCDAP/RELAP5 application to CANDU6 fuel channel analysis under postulated LLOCA/LOECC conditions , 2009 .
[92] Chang-Kuo Chen. A Petri net design of FPGA-based controller for a class of nuclear I&C systems , 2011 .
[93] H. S. Kang,et al. Improvement of the Post-Blowdown Fuel Channel Analysis Model of Candu for a 35% RIH Break LOCA Without ECC , 2004 .
[94] P. Gulshani,et al. Stability of natural-circulation flow in a candu-type fuel channel , 1987 .
[95] M. Lawford,et al. Application of Tabular Methods to the Speciflcation and Veriflcation of a Nuclear Reactor Shutdown System , 2001 .
[96] John C. Knight,et al. Safety critical systems: challenges and directions , 2002, Proceedings of the 24th International Conference on Software Engineering. ICSE 2002.
[97] Hho-Jung Kim,et al. Analyses on fluid flow and heat transfer inside Calandria vessel of CANDU-6 using CFD , 2006 .