Artificial Intelligence and Other Innovative Computer Applications in the Nuclear Industry

Artificial Intelligence and Other Innovative Computer Applications in the Nuclear Industry

Edited by

M. Catherine Majumdar Westinghouse Idaho Nuclear Corporation Idaho Falls, Idaho

Debu Majumdar u.s. Department of Energy Idaho Operations Office Idaho Falls, Idaho

and

John I. Sackett Argonne National Laboratory West Idaho Falls, Idaho

Plenum Press • New York and London

Library of Congress Cataloging in Publication Data

American Nuclear Society Topical Meeting on Artificial Intelligence and Other In­novative Computer Applications (1987: Snowbird, Utah)

Artificial intelligence and other innovative computer applications in the nuclear in­dustry / edited by M. Catherine Majumdar, Debu Majumdar, and John I. Sackett.

p. cm. "Proceedings of the American Nuclear Society Topical Meeting on Artificial In­

telligence and Other Innovative Computer Applications, held August 31-September 2, 1987, in Snowbird, Utah"- T.p. verso.

Includes bibliographies and indexes. ISBN-13: 978-1-4612-8290-7 e-ISBN-13: 978-1-4613-1009-9 DOl: 10.1007/978-1-4613-1009-9 1. Nuclear industry-Data processing-Congresses. 2. Artificial intelligence­

Industrial applications-Congresses. I. Majumdar, M. Catherine. II. Majumdar, D. (Debu) III. Sackett, John I. IV. Title. TK9006.A48 1987 88-9396 621.48'3'028563 -dcl9

Proceedings of the American Nuclear Society Topical Meeting on Artificial Intelligence and Other Innovative Computer Applications, held August 31-September 2, 1987, in Snowbird, Utah

© 1988 Plenum Press, New York Softcover reprint of the hardcover 1st edition 1988 A Division of Plenum Publishing Corporation 233 Spring Street, New York, N.Y. 10013

All rights reserved

CIP

No part of this book may be reproduced, stored in a retrieval system, or transmitted in any form or by any means, electronic, mechanical, photocopying, microfilming, recording, or otherwise, without written permission from the Publisher

PREFACE

This conference brought together experts from 15 countries to discuss application of Artificial Intelligence (AI) techniques to the nuclear industry. It was apparent from the meeting that even those active in the field were surprised at the extent of work and the progress made. There was a strong impression that application of this technology to nuclear power plants is inevitable. The benefits to improved operation, design, and safety are simply too significant to be ignored.

This is a much different conclusion than might have been reached a few years ago when the technology was new and people were struggling to understand its significance. We believe that this meeting reflects a major turning point for the technology. It has moved from being a topic understood only by specialists to a situation where users are the most active people in the field.

A broad array of innovative work is described from all of the participating countries. The activity in the u.s. is large and diverse. Although there is no nationally focussed policy for AI research in the U.S., many of these activities are reported here. Japan and France have a strong drive to integrate AI technology into their nuclear plants, and this is reflecteq in these proceedings.

There is now a sense of excitement about what can be achieved, a refreshing departure from the often defensive posture taken in nuclear power development these days. The excitement stems from recognition that the technology has the potential to greatly expand our capabilities as designers and operators. To take but one example, great strides have been made in developing systems that can diagnose the condition of the plant and provide options for response. Artificial Intelligence work has not yet led to extensive automation, but it will.

There was much discussion at the meeting about the fact that Artificial Intelligence is a poor title for this work: Knowledge engineering comes closer to what is being achieved. We hope that you will find these proceedings both interesting and useful. This is an emerging field that will affect us all.

J. Curtis Haire, General Chairman

Debu Majumdar and John I. Sackett, Technical Program Co-Chairmen

v

MEETING OFFICIALS

General Chairman

Program Co-Chairman

Program Co-Chairman

Arrangements

Finance

Registration

Exhibits

Publications

Public Information

Guest Program

Registration Desk

CO-SPONSORS

J. Curtis Haire EG&G Idaho, Inc.

Debu Majumdar U.S. Department of Energy Idaho Operations Office

John I. Sackett Argonne National Laboratory-West

Richard W. Lindsay Argonne National Laboratory-West

Orville R. Meyer EG&G Idaho, Inc.

Carl H. Cooper EG&G Idaho, Inc.

Glen A. Mortensen EG&G Idaho, Inc.

M. Catherine Majumdar Westinghouse Idaho Nuclear Co.

George A. Freund Science Applications, Inc.

Karen Sackett

Betty Haire and Marge Lindsay

Idaho Section of the American Nuclear Society European Nuclear Society ANS Human Factors Division ANS Remote Systems Technology Division

vi

PROGRAM COMMITTEE

Technical Program Co-Chairmen - Debu Majumdar, U.S. Department of Energy - Idaho Operations Office and John I. Sackett, Argonne National Laboratory-West

A.D. Alley ............. General Electric Company Hakan Andersson ........ Studsvik Energiteknik Bill Bertch ............ General Dynamics, Inc. Paul Blanch ............ Northeast Utilities Service Co. William V. Botts ....... EI International, Inc. Michael Bray ........... EG&G Idaho, Inc. John S. Brtis .......... Sargent and Lundy David Cain ............. EPRI Allen Christie ......... Westinghouse Electric Corp. Robert Colley .......... EPRI Gail A. Cordes ......... Intermountain Technologies, Inc. Brent Dixon ............ EG&G Idaho, Inc. James Dukelow, Jr ...... Boeing Computer Service Robert Engelmore ....... Stanford University Jerry D. Griffith ...... U.S. Department of Energy Dennis Harrison ........ U.S. Department of Energy James P. Jenkins ....... U.S. Nuclear Regulatory Commission C. Edward Johnson ...... Westinghouse Idaho Nuclear Co. Harry Julian .......... , Volian Enterprises, Inc. Jan G. Kretzschmar ..... SCK/CEN Informatics Bob Lang ............... Middle South Services Company Henry Makowitz ......... EG&G Idaho, Inc. William Nelson ......... EG&G Idaho, Inc. Pedro J. Otaduy ........ Oak Ridge National Laboratory Howard Rohm ............ U.S. Department of Energy Gary Sandquist ......... University of Utah Donald Schurman ........ EG&G Idaho, Inc. Devin Smith ............ S.U.N.Y., Stony Brook Bob Stiger ............. Delian Corporation Al Sudduth ............. Duke Power Company Gilles Zwingelstein .... Electricite de France

PAPER REVIEWERS

John Sackett ........... Argonne National Laboratory-West Debu Majumdar .......... U.S. Department of Energy Jan Kretzschmar ........ SCK/CEN Informatics Hakan Andersson ........ Studsvik Energiteknik Paul Blanch ............ Northeast Utility Service Co. John Brtis ............. Sargent and Lundy Henry Makowitz ......... EG&G Idaho, Inc. Mike Bray .............. EG&G Idaho, Inc. Al Sudduth ............. Duke Power Company Gary Sandquist ......... University of Utah Jim Jenkins ............ U.S. Nuclear Regulatory Commission Brent Dixon ............ EG&G Idaho, Inc. Rich Mark .............. Volian Enterprises Jim Dukelow ............ Boeing Computer Service Gail A. Cordes ......... Intermountain Technologies, Inc. Pedro J. Otaduy ........ Oak Ridge National Laboratory C. Edward Johnson ...... Westinghouse Idaho Nuclear Co. Bill Nelson ............ EG&G Idaho, Inc. Howard Rohm ............ U.S. Department of Energy Bob Stiger ............. Delian Corporation

SESSION CHAIRMEN

A.D. Alley General Electric Co.

H. Andersson Studsvik Energiteknik

T. Bjorlo Institutt for Energiteknikk

P. Blanch Northeast Utilities Service Co.

W.V. Botts EI International, Inc.

M.A. Bray EG&G Idaho, Inc.

J. Brtis Sargent and Lundy

P.C. Cacciabue Joint Research Centre Ispra

D. Cain Electric Power Research

Institute

A. Christie Westinghouse Electric Corp.

G.A. Cordes Intermountain Technologies, Inc.

B. Dixon EG&G Idaho, Inc.

J. Dukelow, Jr. Boeing Computer Service

L. Ho Institute of Nuclear Energy

Research

E. Hollnagel Computer Resources International

A. Jaeschke Nuclear Research Center

J. Jenkins u.s. Nuclear Regulatory

Commission

viii

C.W. Johnson Westinghouse Idaho Nuclear

Co.

H. Julian Vol ian Enterprises, Inc.

T. Kiguchi Hitachi Energy Research

Laboratory

J. Kvetzchmar SCK/CEN Informatics

R.W. Lindsay Argonne National Laboratory

West

H. Makowitz EG&G Idaho, Inc.

P. Malvache CEA, France

K. Monta Nippon Atomic Industry Group

J. Mott EI International, Inc.

W. Nelson EG&G Idaho, Inc.

J. Panoussian Framatome

Y. Shinohara Japan Atomic Energy Research

Institute

D. Smith SUNY at Stony Brook

Y. Souchet CEA, France

A. Sudduth Duke Power Company

J.B. Thomas CEA, France

G. Zwingelstein Electricite de France

CONTENTS

CHAPTER 1 INTERNATIONAL OVERVIEW

Knowledge Based Systems for Nuclear Applications in Germany. . . . . . . . . . . . . . . . .

F. Schmidt

Applications of Artificial Intelligence in the u.S.

3

Nuclear Industry . . . . . . . . . . 11 R.E. Uhrig

NKA/INF - Advanced Information Technology. • • • . . .• 21 V. Andersen, K. M¢llenbach, R. Heinonen, S. Jakobsson,

T. Kukko, 0. Berg, J.S. Larsen, T. Westgard, B. Magnusson, H. Andersson, C. Holmstrom, B. Brehmer and R. Allard

A Survey of Framatome's Expert Systems Activity. . . . .. 29 D. Delaigue and M. Grundstein

Artificial Intelligence Applications for Operation and Maintenance: Japanese Industry Cases ......... 37

M. Itoh, I. Tai, K. Monta and K. Sekimizu

Development in the Application of Knowledge Base Systems in the Canadian Nuclear Industry. . . . . . . . 45

J.W.D. Anderson, A. Natalizio, and J.E.S. Stevens

CHAPTER 2 ROBOTICS AND MAINTENANCE

Beyond Human Performance. F.E. Gelhaus

53

Expert Robots in Nuclear Plants . . .. ........ 59 J.S. Byrd, J.J. Fisher, K.R. DeVries, and T.P. Martin

Reliability Analysis of the Inspection by a Man and a Robot for the Maintenance of a Nuclear Power Plant . . 69

Y. Oka, H. Araki, and Y. Togo

Automatic Scheduling of Maintenance Work in Nuclear Power Plants ..................... 77

T. Kasahara, Y. Nishizawa, K. Kato, and T. Kiguchi

The Instrumentation Calibration Reduction Program (ICRP) at Northeast Utilities ................ 85

R. Wyckoff and P. Blanch

A Knowledge-Based Assistant for Valve Maintenance Planning . . . . . .. ....... . . . . . 95

M.J. Winter, R.A. Danofsky, B.I. Spinrad, and K. Howard

Steam Generator Inspection Planning Expert System. . . . . 103 P. Rzasa

CHAPTER 3 ALARM AND SIGNAL VALIDATION

Extra: A Real Time Knowledge-Based Alarm System ...... 113 J. Ancelin, J.P. Gaussot, and P. Legaud

A Nuclear Reactor Alarm Display System Utilizing AI Techniques for Alarm Filtering ..... . .. 119

D. Corsberg and L. Johnson

An Expert System for Alarm Diagnosis and Filtering .... 127 J.T. Robinson and P.J. Otaduy

Applying AI Techniques to Improve Alarm Display Effectiveness . . .. ....... ..... 135

J.M. Gross, S.A. Birrer, and D.R. Corsberg

Development of Knowledgebase System for Assisting Signal Validation Scheme Design . . . . . . . . . . . 141

M. Kitamura, T. Baba, T. Washio, and K. Sugiyama

An Expert System for Sensor Data Validation and Malfunction Detection . . . . .. ....... 149

S. Hashemi, B.K. Hajek, and D.W. Miller

Smart Sensor Application to Nuclear Plant Thermocouple Channels . . . . . . . .

N.S. Cannon, J.D. Martin, B.A. Patterson, J.L. and B. D. Zimmmerman

An Integrated Approach for Signal Validation in Nuclear Power Plants . . . . . . . . .

Stringer,

B.R. Upadhyaya, T.W. Kerlin, O. Gr6ckler, Z. Frei, L. Qualls, and V. Morgenstern

CHAPTER 4 EMERGENCY RESPONSE

Potential Applications of Advanced Information Technology

157

167

in Emergency Management.. . ........... 177 H. Andersson and C. Holmstrom

x

OPA: Operator Advisor, an Emergency Response Guide and Monitoring System. . . .. . ..... 185

L. Mampaey, P. Moeyaert, F. Bastenaire, F. Casier, and N.D. Chi

Reactor Emergency Action Level Monitor .......•.. 189 R.A. Touchton

Development of an Accident Management Expert System for Containment Assessment. . . ..•... 199

W.R. Nelson, D.E. Sebo, and L.N. Haney

An Expert System for Improving Nuclear Emergency Response ....................... 205

A. Salame-Alfie, G.C. Goldbogen, R.M. Ryan, W.A. Wallace, and M.L. Yeater

The Knowledge-Based Off-Site Emergency Response System for a Nuclear Power Plant . . . . . . • • . . . . . . 213

L. Ho, W. Loa, and C. Wang

Reactor Safety Assessment System . . . . . . . . . . 221 D.E. Sebo, M.A. Bray, and M.A. King

A Production-Rule Analysis System for Nuclear Plant Monitoring and Emergency Response Applications. .. 231

M. Ragheb, L. Tsoukalas, T. McDonough,and M. Parker

CHAPTER 5 PROCESS DIAGNOSTICS AND TRANSIENT ADVISOR

A Generalized System State Analyzer for Plant Surveillance. . .......•......... 241

J. Mott, R. King and W. Radtke

Developing an Expert System for Monitoring Power Plant Processes . . . . . . . . . . . . . . . . 251

K. Ari, H. Jyrki and R. Jukka

The DISYS Real-Time Diagnostics/Control System and Its Application to the EBRII. . . . . . . . . . . 259

A.M. Christie and R.W. Lindsay

Accident Diagnosis and Prognosis Aide (ADPA) . . . . . . . 269 A.D. Gunter and R.A. Touchton

Sextant: An Expert System for Transient Analysis of Nuclear Reactors and Integral Test Facilities ... 273

N. Barbet, M. Dumas, G. Mihelich, Y. Souchet and J.B. Thomas

Deep Knowledge Expert System for Diagnosis of Multiple­Failure Severe Transients in Nuclear Power Plant. . . 281

R.P. Martin and B. Nassersharif

Digital Data Monitoring Display and Logging - an Approach to Intelligent Data Display and Control ... 289

E.P. Ficaro and D.K. Wehe

xi

MOAS: A Real-Time Operator Advisory System ........ 297 I.S. Kim and M. Modarres

Artificial Intelligence Expert System for Nuclear Power Plant Control and Maintenance • . . . . . . . . 305

G.B. Westrom

CHAPTER 6 HUMAN-MACHINE INTERFACE

An Expert System for Modelling Operators' Behaviour in Control of a Steam Generator . • . . . • . . . . . 313

P.C. Cacciabue, G. Guida and A. Pace

Knowledge-Based Dialogue in Intelligent Decision Support Systems ................. 321

E. Hollnagel

A Map Multilevel System as a Man-Machine Interface for Emergencies Management. . . . . . . • • . . . . . 331

F. Argentesi and N.M. Avouris

A Model-Based Display. . . . . . . . . . . . . . 337 L. Beltracchi

Focusing on the Human Factor in Future Expert Systems ... 345 S.E. Gordon

Operator Performance with the Halo II Advanced Alarm System for Nuclear Power Plants - A Comparative Study . . . . . . .. ......• • . . . . . . 353

E. Marshall, C. Reiersen and F. Owre

CHAPTER 7 INTELLIGENT DATA BASE DEVELOPMENT

Reactor Emergency Action Level Monitor: Knowledge Acquisition Experiences . . . . . . . . . . . . . . . 363

R.A. Touchton

A Conceptual View Data Model of a Distributed Control and Monitoring System for a Nuclear Power Plant . . . 369

L.E. Fennern

An Approach to Build a Knowledge Base for Reactor Accident Diagnostic Expert System . . .. . ... 375

K. Yoshida, T. Aoyagi, Y. Hirota, M. Fujii, K. Fujiki, M. Yokobayashi and A. Kohsaka

Incorporating "Fuzzy" Data and Logical Relations in the Design of Expert Systems for Nuclear Reactors . . . . 383

M.A.S. Guth

A Nuclear Facility Security Analyzer Written in Prolog .. 393 B.D. Zimmerman

An OPS5-English English-OPS5 Parser and Language Generator . . . . . . . . . . . . . . . . 401

B. Baird, S. Wertheimer, N. Gove and P. Otaduy

xii

PROLGRAF-B: A Knowledge-Based System for the Automated Construction of Nuclear Plant Diagnostic Models . . . 407

S.B. Guarro

CHAPTER 8 PLANT CONTROL SYSTEMS

Application of an AI Method to Optimal Reactor Control Problems ................... 421

Y. Shinohara

Knowledge-Based Systems and Interactive Graphics for Reactor Control Using the Automated Reasoning Tool (ART) System ................... 429

M. Ragheb, B. Clayton and P. Davies

Promises in Intelligent Plant Control Systems ...•... 437 P.J. Otaduy

Using an Integration Development Methodology to Produce a Reactor Control System for the Advanced Test Reactor at the INEL . . . . . . . . . . . . . . . . . 445

R.L. Smith and J.M. Svoboda

Linguistic Control of a Nuclear Power Plant ........ 453 J.J. Feeley and J.C. Johnson

Time-Optimal Control of Reactor Power ........... 461 J.A. Bernard

A Computer Control System for a Research Reactor . . .. 471 K.C. Crawford and G.M. Sandquist

Structure of Controllers for the Direct Digital Control of Reactor Power: Licensing Implications ...... 483

J.A. Bernard

CHAPTER 9 EQUIPMENT DIAGNOSTICS

TRIBES - A CPC/CEAC TRIp ~uffer gxpert £ystem Written in PROLOG . . . . . . . . . . . . . . . . . . . . . . 495

R.B. Lang

CRAW - An Expert System for Nuclear Reactor Cover Gas Alarm Analysis .................... 503

B.D. Zimmerman and J.A. Rawlins

The Use of Deep Knowledge Qualitative Models as a Basis for Real-Time Diagnostic Support Systems for Power Plant Control Room Operators ............. 509

G.H. Williams and A.J. Hudson

An Expert System for Diesel Generator Diagnostics D.C. Bley, J.W. Read, S. Kaplan, J.K. Liming,

N.M. Brosee and D.W. Hanley

517

xiii

Early Detection and Diagnosis of Disturbances in Nuclear Power Plants. . . . . . . . . 529

T.J. Bj~rlo, 0. Berg, R.E. Grini and M. Yokobayashi

Macroscopic Mass and Energy Balance for Nuclear Plant Diagnostics Using Fuzzy Logic . . . . . . . . . . . . 539

J.A. Hassberger and J.C. Lee

Power Plant Experience with Artificial Intelligence Based, On-Line Diagnostic Systems . . . . . . . . . . 547

R.L. Osborne and M. Coffman

An On-Line Diagnostic Expert System. . . . . • . . . . • . 555 L. Felkel

Developing an Expert System for Fault Diagnosis of a Turbo Generator Group Using an OPS5 Production Rules Programming Environment. . . . . . . 565

C. Balducelli and M. Gallanti

Expert System for Nuclear Power Plant Feedwater System Diagnosis. . . . . . . . . . . .. . ... 573

R. Meguro, Y. Kinoshita, T. Sato, Y. Yokota, and M. Yokota

A New Method of Knowledge Processing for Equipment Diagnosis of Nuclear Power Plants . . .. .... 581

M. Fujii, A. Fukumoto, I. Tai and T. Morioka

CHAPTER 10 OPERATION ANALYSIS AIDS

THEXSYST - An Intelligent Monitor for Reactor Safety Calculations .•................... 591

B. Burger and F. Schmidt

Development of "ADRA" - An Alara Design Review Assistant . 599 J.S. Brtis

Documentation of Knowledge in the Development of CLEO, a Refueling Assistant for FFTF. . • • . . . . . 607

D.E. Smith

ATHENA AIDE - An Expert System for ATHENA Code Input Model Preparation . . . . . . . . • . . . . . 611

R.K. Fink, R.A. Callow, T.K. Larson and V.H. Ransom

A BWR Fuel Channel Tracking System . . . . . . R.S. Reynolds

Fuel Insert Shuffler: Development . . .

J. Naser, R. Colley, S. Engle

A Case Study of Expert System

J. Gaiser, T. Brookmire and

. . 617

. . . 625

An Expert System for Operational Control of PWR Cores ... 635 O.J.M. Peixoto, B. Frogner and J.M. Holzer

An Automated Search Procedure for Fuel Shuffling in PWRs Including Rotation Effects. . .... 645

A.H. Robinson, J.O. Heaberlin and G.L. Wang

xiv

Plant Status Monitor System Description .......... 653 W.A. Prather and G.A. Sly

CHAPTER 11 PLANT OPERATIONS AND SUPPORT

An Expert System for Spare Parts Inventory Control . . . . 659 K.Y. Kim, P.Y.C. Chen and D. Okrent

INSPECTR: A Power Plant Performance Diagnostic Expert System Using Evidential and Model-Based Reasoning . . 663

T. Kessler, G. Liu, B. Frogner, D. Gloski, P. Wallace and D. Shieh

Production-Rule Analysis System for Nuclear Plant Technical Specifications Tracking . . . . . . . . . . 673

M. Ragheb, M. Abdelhai and J. Cook

The Use of PROLOG for Computerized Technical Specifications . . . . . . . . . . . . .

L.M. Lidsky, D.D. Lanning, A.B. Dobrzeniecki, K. Meyers and T.G. Reese

Emergency Procedures Tracking System for Nuclear Power Plants. . . . . . . . . . ...

W. Petrick, K. Ng, C. Stuart, D. Shen, D. Cain, B. Sun and C. Christensen

A Computerized System for Improved Management and

681

. . . . 689

Execution of Plant Procedures . . . . . . . . . 697 M.H. Lipner, R.G. Orendi, A.J. Impink and

R.A.Mundy

Computer Aided Procedure Execution . . . . . . . . . . . . 705 Fridtjov 0wre

Interface of an Expert System with On-Line Data for Technical Specification Monitoring.. . .... 715

W.H. Schlegelmilch and R.P. Jefferis

Integrated Disturbance Analysis (IDA), a Basis for Expert Systems in Nuclear Power Plants.. . ... 721

W. Bastl

Development of a Knowledge-Based System for Loop Diagnosis. . . . .. . ........••.. 731

L. Liao, H. Tang and S. Chen

Knowledge Based Diagnostics in Nuclear Power Plants .... 739 F. Baldeweg, U. Fiedler, F.P. Weiss and M. Werner

CHAPTER 12 PROBABILISTIC RISK ASSESSMENT

An Expert System for Fault Tree Analysis ...•..•.. 747 B. Frogner

xv

Reasoning and Representation in RiTSE ........... 751 S.A. Epstein

EXPRESS: An Expert System to Perform System Safety Studies. . . . . . .. . ...... 761

C. Ance1in, P. Le, S. De Saint-Quentin and N. Vi11atte

The Development of an Expert System for Finding Fragility Curves of Building Structural Systems in the Preliminary Design Stage . . . . . . . 769

L. Yee and D. Okrent

A PRA-Based Data Analysis for Use in Computerized Decision Aids • . . . . . . . . . . . . • . . . 775

S. Arueti and G. Aposto1akis

An Intelligent Man-Machine Interface for Diagnosis . . . . 783 E. Fi1shtein and P. Rzasa

Time-Dependent Reliability Analysis of Nuclear Reactor Operators Using Probabilistic Network Models .................... 791

Y. Oka, K. Miyata, H. Kodaira, S. Murakami, S. Kondo and Y. Togo

Using Risk Based Tools in Emergency Response . . . . . . . 799 B.W. Dixon and K.G. Ferns

CHAPTER 13 ADVANCED CONCEPTS AND NON-NUCLEAR APPLICATIONS

Heuristic Simulation of Nuclear Systems on a Supercomputer Using the HAL-1987 General-Purpose Production-Rule Analysis System . . . . . . . . . . . 809

M. Ragheb, D. Gvi110 and H. Makowitz

SOPHIE: An Expert System for the Selection of Hazard Evaluation Procedures ............. 817

S.J. Nicolosi

Advanced Technology for Nuclear Powerp1ants ........ 819 H.H. Rohm

Efficient Diagnostic Search Via Information Entropy Reduction . ................... 827

E.L. Fi1shtein

The Structure of an Expert System to Diagnose and Supply a Corrective Procedure for Nuclear Power Plant Malfunctions. . . . . . . . . .. .. 837

B.K. Hajek, J.E. Stasenko, S. Hashemi, R. Bhatnagar, W.F. Punch III and N. Yamada

CAA - An Expert System for Analysis Management

xvi

in Chemical Processes . . . . . . A. Jaeschke, W. Konrad, H. Orth, o. Tjandra,

and G. Zil1y

845

Diagnostics Aid for Mass Spectrometer Trouble-Shooting . . 853 E.E. Filby, R.A. Rankin and G.W. Webb

Uncertainty Propagation in Production-Rule Systems Using a Probability-Possibility Approach ....... 863

L. Tsoukalas and M. Ragheb

SIA: A Safeguard Inspector Assistant to Plutonium Isotopic Composition Measurements by Means of Gamma Ray Spectrometry. . . . . . . . . . ... 875

B. Carniel, G. De Grandi and A. Stefanini

Overview of DIVA: An Expert System for Turbine-Generator Diagnosis ...................... 883

B. Ricard, B. Monnier, J. Morel, J.M. David, J.P. Krivine, and J.P. Tiarri

A Computerized Experiment for Comparison Between Methods of Uncertainty Propagation. . . . . . . . . . 891

S. Arueti

Attendees. 899

Index. • • 907

xvii