This Specialists' Meeting on In-core Instrumentation and Reactor Core Assessment is the fourth in a series initiated by the NEA Committee on Reactor Physics and continued by the NEA Nuclear Science Committee. The first meeting was held in Fredrikstad, Norway, in 1983, the second at Cadarache, France, in 1988 and the third in Pittsburgh, USA in 1991.
The purpose of the meeting was to review the improvements in the methods used to gather and interpret information on the conditions of the reactor core. Thirty-nine papers were presented in six sessions covering radiation sensors, safety analysis, system and validation, other miscellaneous measurements, core monitoring and core performance. One hundred and nine participants from nineteen countries and International Organisations attended the meeting.
Participation from non-OECD countries was made possible thanks to the collaboration of the Working Group on Nuclear Power Plant Control and Instrumentation (IWGNPPCI) of the International Atomic Energy Agency.
The NEA wishes to thank the authors and session chairmen for their contribution to the success of the meeting. It also wishes to express its appreciation to the Japan Atomic Energy Research Institute (JAERI) for arranging and hosting the meeting.
The following papers presented at the meeting are available in Acrobat
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The complete set of papers as PDF files (not including the html files) can be retrieved as ic96.exe (4.2 Megabytes)
TABLE OF CONTENTS
SESSION 1: CORE MONITORING – A
Summary: Oldrich Erben, Chairman
An On-line Adaptive Core Monitoring System
J.A. Verspeek, J.C. Bruggink, J. Karuza (The Netherlands)
A Benefit Assessment of Using In-core Neutron Detector
Signals in
Core Protection Calculator System (CPCS)
S. Han, S-J. Park, P-H. Seong (Korea)
Computer Based Core Monitoring System
P. Swaminathan, P. Sreenivasan (India)
Analytical Evaluation of the Uncertainty of On-line
Axial Power Distribution
Measurement with the Four-section Ex-core Detector
J. Matsumoto, K. Seki, Y. Komano (Japan)
SESSION 2: CORE MONITORING – B
TOPRE & HOTPOINT In-core Monitoring Systems for
WWER-440
Nuclear Power Plants
T. Polák, O. Erben (Czech Republic)
The Extended On-line Core Monitoring Technology with
the Latest
VERONA-u Version
F. Adorján, L. Bürger, I. Lux, J. Végh, Z. Kálya,
I. Hamvas (Hungary)
Application of the Core Surveillance System SCORPIO
at Sizewell B
Ø. Berg, M. McEllin, M. Javadi (Norway and UK))
RINGHALS 2 Core Monitoring Experience
T. Andersson, Ø. Berg, K. Romslo (Norway)
Experience and Evaluation of Advanced On-line Core
Monitoring System
"BEACON" at IKATA Site
N. Fujitsuka, H. Tanouchi, Y. Imamura, D. Mizobuchi, T. Kanagawa,
M. Masuda (Japan)
The BEACON On-line Core Monitoring System: Functional
Upgrades and Applications
W.A. Boyd, R.W. Miller (USA)
SESSION 3: CORE PERFORMANCE ASSESSMENT
Summary: Øivind Berg, Chairman
Reactor Internals Vibration Monitoring in Korean
Nuclear Power Plant
T-R. Kim, S-H. Jung, J-H. Park, S. Choi (Korea)
Utilisation of Self-powered Neutron Detectors for
Reactivity Control
V. Borissenko (Ukraine)
On-line Estimation of Local and Total Core Flow Rate
by Neutron Noise Analysis in BWR
M. Mori, S. Kanemoto, M. Enomoto, S. Ebata (Japan)
Space-dependent Dynamics of PWR
T. Suzudo, E. Türkcan, J. Verhoef (Japan and The Netherlands)
SESSION 4: INSTRUMENTATION
Summary: Jean-Pierre Trapp, Chairman
Direct Experimental Tests and Comparison between
Sub-miniature
Fission Chambers and SPND for Fixed In-core Instrumentation of LWR
G. Bignan, J.C. Guyard, C. Blandin, H. Petitcolas (France)
Characteristics of Self-powered Neutron Detectors
Used in Power Reactors
W.H. Todt (USA)
High Temperature Fission Chambers: State-of-the-art
J-P. Trapp, S. Haan, L. Martin, J-L. Perrin, M. Tixier (France)
Application of the Gamma Thermometer as BWR Fixed
In-core
Calibration System
R. Raghavan, C.L. Martin, A.L. Wirth, T. Itoh, Y. Goto, R. Arai (USA
and Japan)
Experience with Fixed In-core Detectors at Seabrook
Station
J.P. Gorski, R.J. Cacciapouti (USA)
NAJA: A New Non-destructive Automatic On-line Device
for Fuel Assembly
Characterisation and Core Loading Conformity Control
G. Bignan, D. Janvier (France)
SESSION 5: ADVANCED INSTRUMENTATION TECHNOLOGIES
Summary: Joachim Runkel, Chairman
Some New Optical Techniques for Reactor Instrumentation
M. Nakazawa (Japan)
Development of a Distributed Monitoring System for
Temperature and
Coolant Leakage
F. Jensen, E. Takada, M. Nakazawa, H. Takahashi, T. Iguchi, T. Kakuta,
S. Yamamoto (Japan and Sweden)
In-core Measurements of Reactor Internals Vibrations
by Use of
Accelerometers and Neutron Detectors
J. Runkel, E. Laggiard, D. Stegemann, P. Heidemann, R. Blaser, F.
Schmid,
H. Reinmann (Germany and Switzerland)
Overview and Future Development of the Neutron Sensor
Signal
Self-validation (SSV) Project
J-C. Trama, A. Bourgerette, E. Barat, B. Lescop (France)
Fuel Rod Performance Measurements and Re-instrumentation
Capabilities
at the Halden Project
O. Aarrestad, H. Thoresen (Norway)
SESSION 6: SAFETY ANALYSIS
Summary: Masaharu Kitamura, Chairman
Application of Process-monitoring Techniques to Neutron
Noise
Signals from Simulated-coolant-boiling Experiements
H. Schoonewelle, T.H.J.J. van der Hagen, J.E. Hoogenboom (The Netherlands)
Stochastic Pattern Recognition Techniques and Artificial Intelligence
for Nuclear Power Plant Surveillance and Anomaly Detection
L.G. Kemeny
Impact of Core Inertial Properties
on Dynamic Characteristics of
WWER-1000 Reactor Barrels
V. Gribkov (Russia)
SESSION 7: SIGNAL PROCESSING
Summary: Erdinc Türkcan, Chairman
Monitoring the State of the Coolant in a Boiling
Water Reactor
G. Roston, R. Kozma, M. Kitamura (Japan and Argentina)
Decay Ratio Studies in BWR and PWR using Wavelet
Ö. Ciftcioglu, E. Türkcan (The Netherlands and Turkey)
ALPES, a Demonstrator for On-line Core Temperature
Visualising and Processing
A. Lebrun, J-P. Trapp, S. Sala (France)
New Neutron-temperature Noise Methods and their Experimental
Check
on the Reactor VVER-1000
V.I. Pavelko, D.F. Gutsev (Russia)
Reactor Thermal/Hydraulic Processes Monitoring and
Aid to Diagnosis,
Using Acoustical Signal and On-line Calculations
K.N. Proskouriakov (Russia)
SESSION 8: MISCELLANEOUS
Summary: Shigeru Kanemoto, Chairman
Development of a Real-time Plant Simulation System
for BWRs
K. Tominaga, S. Arita, Y. Ishii, H. Sano (Japan)
Investigation of the Pellet-cladding Interaction
Related Issues Including Fuel Rod
Failure by Methods for Identification System with Distributed Parameters
S. Utenkov (Russia)
A Technical System to Improve the Operational Monitoring
of the Ukranian
Nuclear Power Plant Zaporozh’ye (Unit 5)
M. Beyer, H. Carl, P. Schumann, A. Seidel, F-P. Weiß, J. Zschau,
K. Nowak (Germany)
ANNEX 1. List of participants