Proceedingsof the

1996 American Nuclear SocietyInternational Topical Meeting

on

Nuclear PlantInstrumentation, Control

and Human-Machine InterfaceTechnologies, NPIC&HMIT'96

The Nittany Lion Inn,The Pennsylvania State University, USA

May 6-9, 1996Sponsored by:

The Power, Nuclear Operations and Human Factors Divisions andThe Pittsburgh Section of The American Nuclear Society (ANS)

Cosponsored by:

The Electric Power Research Institute (EPRI),US Department of Energy (DOE),

US Nuclear Regulatory Commission (NRC),Three Rivers Chapter of the Human Factors and Ergonomics Society (HFES),

Institute of Electrical and Electronics Engineers (IEEE),IEEE Power Engineering Society Nuclear PowerEngineering Committee (IEEE PES NPEC),

Sociedad Nuclear Mexicana (SNM),Canadian Nuclear Society (CNS),

Atomic Energy Council (AEC) Republic of China,Atomic Energy Society of Japan (AESJ),

European Nuclear Society (ENS, Overseas Co-sponsorship),Korean Nuclear Society (KNS).

Published by theAmerican Nuclear Society, Inc. UB/TIB Hannover

La Grange Park, Illinois 60525 USA

NPIC&HMIT96 PLENARYpagel

Dwayne Fry (ORNL)NPIC&HMIT93 General Chair

Robert M. Edwards (Pern State)NPIC&HMIT96 General Chair

Forrest RemickFormer NRC Commissioner

"Meeting Dedication to Montv Schultz"

William T. RussellDirector, Nuclear Reactor Regulation, U.S. NRC

"Digital Systems in Nuclear Plants - Looking to the Future"

Sterling FranksAssociate Director, Engineering Technology Development,

Office of Nuclear Energy, Science and Technology, U.S. DOE

Robert E. UhrigNP1C&HMIT96 Honorary Chair

Distinguished Scientist,Oak Ridge National Laboratory and

Distinguished Professor of Engineering,The University of Tennessee

"An International Persoective on NPIC&HMTT"

Plenary Panel Discussion:"Nuclear Power Plant Instrumentation and

Control, Then, Now and the Future"

Moderated by Don W. MillerNPIC&HMTT'96 Technical Program Chair

Professor and Chairman of the Nuclear Engineering Program,The Ohio State University

Plenary Participants:Walter H. Esselman (EPRI)

John M. Gallagher (U.S. NRC)Britton P. Grim (GE Nuclear Energy)

John E. Myers (John E. Myers & Associates)J. Brian Reid (Westinghouse Electric Corporation)

Improvements for Steam Generator Control

Session Chair: Inn Seock Kim (KAER1/BNL)Topic Organizer: Kee-Choon Kwon (KAREI)

Development of Feedforward Compensator for PWRSteam Generator Water Level Control at Low PowerOperation / Jae-kee Yun, Jun-mo Koo, Young-ryul Lee,Ik-ho Chang (KAERI), and Joon Lyou (ChungnamNational University) 13

Optimized Feedforward Control for Wide RangeOperations of Steam Generators with ConventionalFeedback Control / Yangping Zhao, Robert M. Edwards,and Kwang Y. Lee (Penn State) 19

A Study on H_ Robust Control for the Nuclear SteamGenerator System / Seong Hoon Yook, Un Chid Lee(Seoul National University), and Jung In Choi(Kyungwon University). 25

Design of an Adaptive GPC with Input FeedbackStructure: Application to Steam Generator / Chang HwoiKim, Chang Shik Ham, In Soo Gu, Jae Chang Park(KAERI), and Sang Jeong Lee (Chungnam NationalUniversity) 33

Fuzzy Controller for the Steam Generator Water LevelBased on Real-time Tuning Algorithm / Chul-HwanJung, Kee-Choon Kwon, Joe-Chang Park, Soon-Ja Song,and Chang-Shik Ham (KAERI) 41

Application of Neural Network for PWR Steam GeneratorWater Level Control at Low Power Operation / Hee-HwanHan, Ho-Chang Jung, Young-Ryul Lee, See-Chae Jeong(KAERI), and Kem-Jung Kim (Chungnam NationalUniversity) 49

Genetic Algorithm Based Feedforward and FeedbackControl for Wide Range Operations of Nuclear SteamGenerators / Yangping Zhao, Robert M. Edwards, andKwang Y. Lee (Penn State) 53

I&C Design and Validation Methods

Session Chair and Topic Organizer.Steve Arndt (U.S. NRC)

New Cad for Designing Instrumentation and ControlS y s t e m s / Philippe Castillejos (Electricity de France) . . . 6 3

Development of the Instrumentation and ControlFunctional Test Facility / Kee-Choon Kwon, Soon-JaSong, and Won-Man Park (KAERI) 69

Design of a PC-Based Feedwater Heater SimulationSystem for Monitoring and Control / K. Kavaklioglu andB. R. Upadhyaya (University of Tenneessee) 77

Use of Simulators for Instrument and Control SystemEvaluation / B. K. Hajek, D. W. Miller, Y. Cai, A.Kauffman, and G. Toth (Ohio State) 85

A Study of Intelligent Design Tool System for theDesigning of Nuclear Power Plant / Bong-Ki Kim,Kyong-Ho Lee, Tae-Hoon Lee, Yoon-Hee Lee, and Sung-Rae Kim (KAERI) 91

Dynamic Testing and Simulation of Digital ControlSystems for Boiling Water Reactors / James A. Mowrey(The Foxboro Company), S. I. Abdel-Khalik (GeorgiaInstitute of Technology), and Phillip R. Boylan (TouchBase Computing) 97

Emulation of a Dynamic Safety System ReactorProtection System for a US light Water Reactor / AndrewC. Kauffman, Gabor L Toth, Brian K. Hajek, Don W.Miller, Jeff R. Fluhrer (Ohio State), and Graham Adams(AEA Technology) 105

Advanced Monitoring of Reactor Core Systems #1

Session Chair: Norman Fletcher (DOE)Topic Organizer: Robert M. Edwards (Penn State)

The Development of New On-Line Core MonitoringSystem "TIARA" / Yoko Kobayashi and Sugako Uchida(Toden Software Inc.) 113

Development of a Simulation Based ReactorSurveillance/Advisory System / Andrew Walton andMankit Ray Yeung (The University of Hong Kong) 129

In-core Monitoring System (ICMS) for WER-Reactors /Valentin I. Mitin (RRC "Kurchatov Institute") 137

Radiation Monitoring Systems

Session Chair and Topic Organizer:William A. Jester (Penn State)

Development of a Carbon-14 and Tritium GaseousEffluent Monitor / Khalid M. Alam and William A.Jester (Penn State). 147

An Automatic On-Line Discharge Water RadioactivityMonitoring System Developed for Nuclear Power Plants/ Der-Sun Lee, Shian-Shing Shyu, Chung-Lin Lee, andChung-Jen Chen (Institute of Nuclear Energy Research,Taiwan) 155

Nuclear Plant Accident Instrumentation / E. Matatagui,M. Miller, S. Thorp, and J. Villanueva (National AtomicEnergy Commission of Argentina) 163

Surrounding Radiation Monitoring Station / E.Matatagui, Carlos G. Hofer, Eduardo J. Maino, and JulioS. Zalcman (National Atomic Energy Commission ofArgentina) 171

Safety Critical Software #1

Session Chair: Poong Hyun Seong (KAIST)Topic Organizer: Leo Beltracchi (U.S. NRC)

PLC Based DESFAS in Nuclear Power Plant / Sung Kim,Jang Sik Moon, Hyun Shin Park, and Jai Bok Han(KAERI) 179

Programmable Logic Controller-Based Prototype DigitalPlant Protection System / Hung-Jun Kim, Hee-HwanHan, Jun-Mo Koo, Young-Ryul Lee (KAERI), and Kern-Joong Kim (Chungnam National University) 183

PLD Based Reactor Protection System / Sung Kim, Ik HoJang, Young Ryul Lee, Jun Mo Koo, and Jai Bok Han(KAERI) 189

Enhancing Operator Performance throughAdvanced HMI Technologies

Session Chair Josi March-Leuba (ORNL)Topic Organizer: James D. White (ORNL)

A Cooperative Real-Time Simulation for EvaluatingMan-Machine Interfaces in the Simulated Main ControlRoom Environment of a Generic PWR Nuclear Plant /Kyung H. Cha, Hyun C. Lee, Won M. Park, Kee C.Kwon, and In S. Koo (KAERI) 197

Improving Nuclear Power Plant Safety Parameter DisplaySystem Technology / Madeline Anne Feltus (PennState) 203

Operators' Use of Alternative Soft Control Prototypes ina Simulated Control-Room Task / Douglas G. Hoeckerand Emilie M. Roth (Westinghouse STC) 209

"GARANT" - Automated System for Safety Monitoring,Control, Analysis and Safe Operation Ensuring ofNuclear Power Plants / Igor D. Rakitin, Semion D.Malkin, Vladimir P. Sivokon, and Victor K. Khromov(RRC Kurchatov Institute) 217

Applications of Fuzzy Logic and Neural Networks

Session Chair and Topic Organizer:Masaharu Kitamura (Tohoku University)

Development of a Multistage Neural Network UsingLocal Learning Rules / R. B. Michaels and B. R.Upadhyaya (University of Tennessee). 227

A Logarithmic Neural Network Architecture for PRAApproximation / J. Wesley Hines (University ofTenneessee) 235

Identification of Transient in Nuclear Power Plant UsingAdaptive Template Matching with Neural Network /Euisang Jeong, Kazuo Furuta, and Shunsuke Kondo(University of Tokyo) 243

Simulation of the Balance of Plant of a Nuclear PowerPlant by Neural Networks / Chaung Lin, Shih-ChungChang, and Kuan-Jau Lin (National Tsing HuaUniversity) 251

Qualitative Fuzzy Simulation for On-line AccidentsPrediction in Nuclear Power Plants / Fu-Hua Chou andCheng-Seen Ho (National Taiwan Institute ofTechnology) 257

Neuro-Fuzzy Models Applied to Full Range SignalValidation in Nuclear Power Plants / Paolo F. Fantoni(OECD Halden Reactor Project) 265

Monitoring of NPP State Using Structural Adaptation ina Neural Signal Processing System / R. Kozma,Masaharu Kitamura, and Shoichi Sato (TohokuUniversity) 273

Use of Research Reactors in I&C Design andValidation #1

Session Chair: Joseph Naser (EPRI)Topic Organizer: Robert M. Edwards (Penn State)

Upgrade of Lungtan Zero Power Research Reactor I&CSystem / Tzu-Chung Yenn and Der-Jhy Shieh (Instituteof Nuclear Energy Research, Taiwan) 281

Testbed for Nuclear Plant Instrumentation and ControlValidation / Robert M. Edwards, K. Y. Lee, and D. E.Hughes (Penn State) 287

Experimental Validation of Optimized FeedfowardControl for Improving Reactor Temperature Response /Richard M. Johns, Shiang-shing Shyu, and Robert M.Edwards (Penn State) 295

Design Considerations in Experimental MultivariableControl of the Penn State TRIGA Reactor Using PassiveManipulation of Coolant Flow / Hans D. Gougar, DanielE. Hughes, and Robert M. Edwards (Penn State) 303

Advances in I&C-HMI with Potential NuclearPlant Application #1

Session Chair and Topic OrganizerH. Meieran (PHD Technologies)

Virtual Environments for Nuclear Power Plant Design /S. A. Brown-VanHoozer, R. C. Singleterry, Jr., R. W.King, D.C. Crites, and R. Magnuson (ANL West) 313

Development of the Schedule Review and RefinementFunction for a Plant Construction Planning System /Yasuhiro Kobayashi, Takeshi Yokota, Kenji Araki,Shirou Nonaka, (Hitachi Laboratory, Hitachi Ltd.), andToshiaki Yoshinaga (Hitachi Works, Hitachi Ltd.) . . . . 319

A Power Plant Distributed Real Tune Simulator withGraphical User Interface / Michael D. Lukas, HamidGhezelayagh, and Kwang Y. Lee (Penn State) 327

Supervisory Control with Fault Detection andAccommodation for Power Plants: a Mixed Fuzzy Logicand LQG/LTR Approach / Adel Ben-Abdennour andKwang Y. Lee (Penn State) 335

International Experience in Upgrade of I&C andHMI Systems

Session Chair and Topic OrganizerH. Gordon Shugars (GAMMA-METRICS)

Computerization of Operation for Nuclear Power Plants /Andrei N. Kossilov and Boris Gueorguiev (IAEA). 345

Computer Based Replacement of Safety I&C Systems atBohunice NPP / Drahomlr tiSka (Nuclear Power PlantsResearch Institute) and Alexander DuchaC (Nuclear PowerPlant Bohunice) (Invited) 353

In-Core Monitoring Systems of WWER Nuclear PowerPlant in Czech and Slovak Republics Status andUpgrading / OldHch Erben (NRI Rei pic, CzechRepublic), TomdS Poldk (NPPRI, Slovak Republic),Josef Rosol (NPP Dukovany, Czech Republic), and J HiSvarn'y (SKODA, Czech Republic) 361

Process Computer Modernization in NPP J. Bohunice /Ladislav Cocher (NPP J. Bohunice) (Invited) 369

Improving Instrumentation & Control at RBMKs(Boiling Water Cooled Graphite Moderated Pressure TubeReactor of Russian Design) InternationalElectrotechnical Commission, IEC-International AtomicEnergy Agency, IAEA / Frigyes Reisch (Swedish NuclearPower Inspectorate (SKI)), R R. lonajtis, V. V.Postnikov (Research and Development Institute), GotzKaiser (Beznau Nuclear Power Plant), Andrei Kossilov(IAEA), Joachim Lorenzen (Eurosim), Walt Lyman(Westinghouse), Adly Wahba (GRS), and Nick Wall(AEA Technology) 375

Modernization of Reactor Control and LimitationSystems in German Powers with the New Digital SafetyI&C System TELEPERM XS / Heinz-Wilhelm Bock andArnold Graf (Siemens) 383

Instrumentation and Control Upgrade Project FinalDecisions / M. Dominique Colin (Electricity de France)(Invited) 389

The Method of Monitor and Control Computer SystemReplacement for Main Control Room of Nuclear PowerPlants / Hideaki Matsuoka, Tomoyuki Kasai, ToshirouNakahara (Toshiba Co.), Youji Horie, and AtsushiAdachi (Touhoku Electric Power Co.) 395

Role of Advanced Technology in NP I&C and HMI

Session Chair and Topic Organizer:Lawrence Lupton (AECL)

Taking Full Advantage of Process Constraints inAdvanced Interface Design / Kim J. Vicente and Jo AnneH. Wang (University of Toronto) 405

Display Navigation Design Issues / Leo Beltracchi (U.S.NRC) 413

Computerized System for Procedures ExecutionMonitoring / M. H. Lipner and L A. Rusnica(Westinghouse Electric Corporation) 421

A Study of Logic Display to Monitor the States of LogicElements / Sungpil Lyu (Semyung University) 429

A Study of the Distributed Processing Based PlantComputer System of Nuclear Power Plant / Kyong-HoLee (KAERI)

A Classroom Analysis Simulator for the Laguna VerdeNuclear Power Plant / Carlos Chdvez-Mercado (Institutode Investigaciones Elictricas) 445

Consideration on the Role of Human and Machine inFuture Nuclear Power Plants / Kazuo Furuta (TheUniveristy of Tokyo) 4 5 1

Perception of Symmetry in Polygon Displays / Esa M.Rantanen and Joseph H. Goldberg (Penn State) 459

EPRI I&C Licensing and Demo Plant Initiatives

Session Chair and Topic OrganizerW. B. Reuland (Mollerus Engineering)

The Process for Development of Guidelines on LicensingDigital I&C Upgrades in Nuclear Power Plants / WilliamB. Reuland (Mollerus Engineering) 469

Experience with Licensing Digital Upgrades Using theEPRI Guideline / Gerry van Noordennen (MillstoneNuclear Power Station) (Invited) 473

Application of the EPRI I&C Maintenance PlanningMethodology for Safety System life Extension / EdgarBrown, Martin Ryan, Mark Stofko (ABB CombustionEngineering), and C. Dan Wilkinson (EPRI) 475

Handbook for Verification and Validation of DigitalUpgrades to Instrumentation and Control Systems /Randall S. May, James A. Woolley (S. Levy, Inc.),Siddharth C. Bhatt, Albert Machiels, and RaymondTorok (EPRI) 477

Status of the Electric Power Research Institute's NuclearInstrumentation and Control Program / Joseph Noser,Raymond Torok, and Dan Wilkinson (EPRI) 483

Licensing Digital Upgrades in 1996 - The IndustryGuideline and the NRC Generic Letter / if. C. Torok(EPRI) and R. T. Fink MPR Associates, Inc.) 493

Panel Discussion:U.S. Nuclear Plant I&C Upgrade Issues

Moderated by Dan Wilkinson (EPRI)

Use of Standards in Safety Critical Systems #1

Session Chair Joel Kramer (U.S. NRC)Topic Organizer: Leo Beltracchi (U.S. NRC)

Qualification of an Advanced Digital Safety System /Werner Bastl and Dieter Wach (Institute for SafetyTechnology (ISTec) GmbH) (Invited) 505

High Integrity Software Guideline Development forNuclear Power Plants / Robert W. Brill (U.S. NRC). 513

Perspectives on Research Needed to Enhance NuclearPlant Safety Software Standards / Shivaji S. Seth andDuane W. Hybertson (The MITRE Corporation) 519

Assessment of Nuclear Consolidated Data BaseDevelopment and Modification at the San Onofre NuclearGenerating Station / Stephen H. Hetrick (SouthernCalifornia Edison) and Edward L Quinn (NaturalResources Engineering). 527

Use of Standards in Nuclear Plant I&C

Session Chair: W. G. Sows (American Electric Power )Topic Organizers: W. G. Sotos (American Electric Power ) and

Edward L Quinn (Natural Resources Engineering)

Measurement-Based Dependability Evaluation forSafety-Grade Digital Systems / Dong Tang, MyronHecht, Herbert Hecht (SoHaR Inc.), and Robert Brill (U.S. NRC). 535

Boiling Water Reactor (BWR), Measurements in theReactor Pressure Vessel (RPV) for Monitoring AdequateCooling within the Core, International ElectrotechnicalCommission, IEC 1343 / Frigyes Reisch (SwedishNuclear Power Inspectorate (SKI)), and Bengt Eliasson(Oskarshamn Nuclear Power Plant) 543

Interpretation of ASME Section XI Test Criteria forInstrumentation Used in Inservice Inspection Testing /M. Scott Bums (Arizona Public Service) and Edward (Ted)L Quinn (Natural Resources Engineering). 551

Development of an International Standard on InstrumentSetpoints Based on ISA S67.04 - 1994 / Edward (Ted) L.Quinn (Natural Resources Engineering) 557

Advanced Process Sensor Technology #1

Session Chair: David E. Holcomb (ORNL)Topic Organizers: David E Holcomb (ORNL) and Revis James

(EPRI)

The Use of Commercial off the Shelf Fiber Optics inNuclear Power Plant Radiation Environments / Don W.Miller), Alvin Liau (Ohio State), Revis James (EPRI),and Mardi C. Hastings (Ohio State) 565

Optical Fiber Sensing Technologies for Nuclear PowerPlants: Sensor Principles and Network Designs / R.Fernandez de Caleya, H. Guerrero, I. Sanz, and A. Pirez-Navarro (Universidad Alfonso X El Sabio) 573

BWR Vessel Water Level Response / William E BergeJr., James C. Raines, and Steven M. Dawson (Fauske &Associates, Inc.) 583

Tune Series Analysis of Nuclear Instrumentation in EBR-II /G. R. Intel (ANL) 591

Incorporation of Neutron Sensors in Dynamic SafetySystems / Don W. Miller, Joseph W. Talnagi, YunfangCai (Ohio State), Paul Harold (AEA Technology), and C.Dan Wilkinson (EPRI). 599

Signal Validation for Nuclear Power Plant Using a Set ofNeural Networks / Heui Youn Park, Seung Hwan Seong,Gwi Sook Jang, In Soo Koo, and Kwang Hyeon Park(KAERI) 615

Instrument Surveillance and Calibration Verificationthrough Plant Wide Monitoring Using AutoassociativeNeural Networks / Darryl J. Wrest, J.Wesley Hines, andRobert E. Uhrig (University of Tenneessee) 621

Neural Networks for Environmental Surveillance: AnAutonomous Measurement System Approach / MohamedA. Abdelrahman, D. Subbaram Naidu, and Kevin L.Moore (Idaho State University) 629

Issues in Team Performance

Session Chair: Randall J. Mumaw (Westinghouse)Topic Organizer: Douglas G. Hoecker (Westinghouse)

Supporting Crew Performance through Group-ViewDisplays / William F. StiMer and John M. O 'Hara (BNL) 639

Crew Performance Issues in Nuclear Power Plant ProcessDisturbances / Angelia L Sebok, Bruce P. Hallbert(OECD Halden Reactor Project), and Dolores S.Morisseau (U.S. NRC) 645

The Use of the Dynamic Flowgraph Methodology inModeling Human Performance and Team Effects / A.Milici, J. S. Wu, and G. Apostolakis (ASCA, Inc.)(Invited) 653

Micro Saint as a Tool to Determine Necessary NuclearPower Plant Operating Crew Size / Ron Laughery, BethPlott (Micro Analysis & Design, Inc.), and Julius J.Persensky (U.S. NRC). 661

Dealing with Operator Reliability

Session Chair William F. Stubler (BNL)Topic Organizer: Douglas G. Hoecker (Wstinghouse)

Communication Errors in Nuclear Power Plants / ValerieE. Barnes (Performance, Safety, and Health Associates,Inc.), Randall J. Mumaw (Westinghouse STC), andIsabelle Schoenfeld (U.S. NRC) 671

The Value of Human Factors Handbooks to HumanFactors Designers in the Nuclear Industry / Catherine M.Burns and Kim J. Vicente (University of Toronto) 679

Can "Theoretical" Training Improve Fault ManagementPerformance? / Christopher N. Hunter, Kim J. Vicente(University of Toronto), and Fumiya Tanabe (JAERI) ... 683

A Reality-Based Method for Assessing Human Errors inPower-Plant Safety / John Wreathall, Dennis C. Bley(The WreathWood Group), Susan E. Cooper (SAIC),Gareth W. Parry (NUS Corporation), William J. Luckas(BNL), Catherine M. Thompson, and Ann Ramey-Smith(U.S. NRC) (Invited) 691

Safety Critical Software #2

Session Chair: James Lyle (NIST)Topic Organizer: Leo Beltracchi (U.S. NRC)

Safety Review Experience of Computerized LogicSystem for Yonggwang Nuclear Power Plant 3 and 4 inKorea / W. Y. Yun, D. I. Kim, J. S. Koh, B. R. Kim, S. H.Oh, and J. H. Lim (Korea Institute of Nuclear Safety) ... 701

Retrofitting I&C Systems in Swedish Nuclear PowerPlants - Fundamental Issues Enlighted - / Erik Johansson( Royal Institute of Technology) 707

Lessons Learned in Installing a Replacement I&CSystem in a WER 1000 Plant / Glenn E. Lang andRobert D. Magee (Westinghouse Electric Corporation). . 715

Integrated I/O Simulator for the Core ProtectionCalculator System Testing / Seung Han, Hee-Seok Park,Soon-Sung Lee, In-Soo Koo, and Chong-Son Chun(KAERI) 719

Safety Significance of High Integrity Reactor ControlSystems / J. Jay Anderson and Bruce M. Cook.(Westinghouse Electric Corporation) 725

Safety Parameter Display System for Kalinin NPP / V. /.Andreev, E. N. Videneev, (Concern "Rosenergoatom"),J. C. Tissot, D. Joonekindt (SEMA GROUP), N. N.Davidenko, G. I. Shaftan (Kalinin NPP), V. G. Dounaev,and V. T. Neboyan (Consyst) 733

Advanced Monitoring of Reactor Core Systems #2

Session Chair: Robert P. Martin (Penn State)Topic Organizer: Robert M. Edwards (Penn State)

Experience in Application of Modern SoftwareEngineering Methods to Operating NPPs I V. A.Khotylev (Delft University of Technology), N. V.Schukin, and I. V. Zonov (Moscow Engineering PhysicsInstitute). 743

Resolving Model Uncertainties in Distributed ParameterSystems for Control and Monitoring Applications /Robert P. Martin and Robert M. Edwards (Penn State). . . 751

The Experimental Procedure for RBMK Void ReactivityCoefficient Measurement Analysis / M. N. Babaytsev, E.V. Burlakov, A. V. Krayushkin, I. D. Rakitin (RRC"Kurchatov Institute"), and I. F. Moiseev (All-RussianResearch Institute) 761

Investigation and Control of the PCI Related IssuesIncluding Fuel Rod Failure by Methods for IdentificationSystem with Distributed Parameters / Sergei A. Utenkov(RRC "Kurchatov Institute") 769

A New System of Neutronics Calculation Support for theOperation of NPPs with RBMK-1000 Reactors / Yury V.Shmonin.V. E. Druzhinin, K.I. Smirnov, D. A. Lysov,L R. Pogosbekjan, S.A. Bychkov (All-RussianResearch Institute for NPP Operation), V. P. Galberg,and Y. B. Chizhevski (Kursk NPP) 777

Monitoring of Power Distribution, Cross Calibrationand Cross-Validation of Full-Core Model and In/Ex CoreMeasurements / Leonid R. Pogosbekjan and Dmitrij A.Lysov (All-Russian Research Institute for NPPOperation) 781

Statistical Analysis of the Power Distribution Accuracyfor Core Monitoring System / Dmitrij A. Lysov, SergeyA. Bychkov, and Leonid R. Pogosbekjan (All-RussianResearch Institute for NPP Operation) 789