Proceedings of the workshop on core monitoring for commercial reactors : improvements in systems and methods : Stockholm, Sweden 4-5 October 1999

297 Pages·2000·11.108 MB·English

by  OECD

Nuclear Science
C
ore Monitoring for Commercial
Reactors: Improvements in
Systems and Methods
Workshop Proceedings
Stockholm, Sweden
4-5 October 1999
N U C L E A R • E N E R G Y • A G E N C Y
 OECD, 2000.
 Software: 1987-1996, Acrobat is a trademark of ADOBE.
All rights reserved. OECD grants you the right to use one copy of this Program for your personal use only. Unauthorised reproduction,
lending, hiring, transmission or distribution of any data or software is prohibited. You must treat the Program and associated materials and any
elements thereof like any other copyrighted material.
All requests should be made to:
Head of Publications Service,
OECD Publications Service,
2, rue Andre´-Pascal, 75775 Paris
Cedex 16, France.
OECD PROCEEDINGS
Proceedings of the Workshop on
C M
ORE ONITORING FOR
C R :
OMMERCIAL EACTORS
I
MPROVEMENTS IN
S M
YSTEMS AND ETHODS
Stockholm, Sweden
4-5 October 1999
Jointly organised by
Vattenfall AB
ABB Atom
Swedish Nuclear Power Inspectorate
OECD/NEA Nuclear Science Committee
NUCLEAR ENERGY AGENCY
ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT
ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT
Pursuant to Article 1 of the Convention signed in Paris on 14th December 1960, and which came into force
on 30th September 1961, the Organisation for Economic Co-operation and Development (OECD) shall promote policies
designed:
− to achieve the highest sustainable economic growth and employment and a rising standard of living in
Member countries, while maintaining financial stability, and thus to contribute to the development of
the world economy;
− to contribute to sound economic expansion in Member as well as non-member countries in the process
of economic development; and
− to contribute to the expansion of world trade on a multilateral, non-discriminatory basis in accordance
with international obligations.
The original Member countries of the OECD are Austria, Belgium, Canada, Denmark, France, Germany,
Greece, Iceland, Ireland, Italy, Luxembourg, the Netherlands, Norway, Portugal, Spain, Sweden, Switzerland, Turkey,
the United Kingdom and the United States. The following countries became Members subsequently through accession at
the dates indicated hereafter: Japan (28th April 1964), Finland (28th January 1969), Australia (7th June 1971), New
Zealand (29th May 1973), Mexico (18th May 1994), the Czech Republic (21st December 1995), Hungary (7th May
1996), Poland (22nd November 1996) and the Republic of Korea (12th December 1996). The Commission of the
European Communities takes part in the work of the OECD (Article 13 of the OECD Convention).
NUCLEAR ENERGY AGENCY
The OECD Nuclear Energy Agency (NEA) was established on 1st February 1958 under the name of the
OEEC European Nuclear Energy Agency. It received its present designation on 20th April 1972, when Japan became its
first non-European full Member. NEA membership today consists of 27 OECD Member countries: Australia, Austria,
Belgium, Canada, Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy,
Japan, Luxembourg, Mexico, the Netherlands, Norway, Portugal, Republic of Korea, Spain, Sweden, Switzerland,
Turkey, the United Kingdom and the United States. The Commission of the European Communities also takes part in
the work of the Agency.
The mission of the NEA is:
− to assist its Member countries in maintaining and further developing, through international
co-operation, the scientific, technological and legal bases required for a safe, environmentally friendly
and economical use of nuclear energy for peaceful purposes, as well as
− to provide authoritative assessments and to forge common understandings on key issues, as input to
government decisions on nuclear energy policy and to broader OECD policy analyses in areas such as
energy and sustainable development.
Specific areas of competence of the NEA include safety and regulation of nuclear activities, radioactive
waste management, radiological protection, nuclear science, economic and technical analyses of the nuclear fuel cycle,
nuclear law and liability, and public information. The NEA Data Bank provides nuclear data and computer program
services for participating countries.
In these and related tasks, the NEA works in close collaboration with the International Atomic Energy
Agency in Vienna, with which it has a Co-operation Agreement, as well as with other international organisations in the
nuclear field.
© OECD 2000
Permission to reproduce a portion of this work for non-commercial purposes or classroom use should be obtained through the Centre
français d’exploitation du droit de copie (CCF), 20, rue des Grands-Augustins, 75006 Paris, France, Tel. [phone], Fax (33-1)
46 34 67 19, for every country except the United States. In the United States permission should be obtained through the Copyright
Clearance Center, Customer Service, [phone], 222 Rosewood Drive, Danvers, MA 01923, USA, or CCC Online:
http://www.copyright.com/. All other applications for permission to reproduce or translate all or part of this book should be made to
OECD Publications, 2, rue André-Pascal, 75775 Paris Cedex 16, France.
FOREWORD
Topics the OECD/NEA Nuclear Science Committee (NSC) has addressed over the years in
co-ordination with the Committee on the Safety of Nuclear Installations (CSNI) include, among others:
• Surveillance and diagnostics.
• In-core instrumentation and reactor core assessment.
A series of symposia and specialists meetings were held covering these topics, the most recent of
which were:
• SMORN-VII: A Symposium on Nuclear Reactor Surveillance and Diagnostics, Avignon,
France, 19-23 June 1995 (proceedings available at http://www.nea.fr/html/science/rsd/).
• Specialists Meeting on In-Core Instrumentation and Reactor Core Assessment, Mito, Japan
14-17 October 1996 (proceedings available at http://home.nea.fr/html/science/rsd/ic96/).
Both of these meetings addressed the issue of signal registration, its processing and interpretation
for the purpose of surveillance, diagnosis and improved operation of nuclear power stations.
The ninth meeting of the OECD/NEA Nuclear Science Committee (NSC), held in June 1998, was
partly devoted to an in-depth discussion of core monitoring. The NSC concluded that it would be
useful to follow up this discussion with a workshop to discuss improvements and further development
of the present monitoring systems and methodologies with the aim of enhancing their ability to handle
modern fuel under present or foreseen operational strategies.
The Workshop on Core Monitoring for Commercial Reactors: Improvements in Systems and
Methods (CoMoCoRe’99) took place from 4-5 October 1999 in Stockholm. It was jointly organised
by Vattenfall AB, ABB Atom and the Swedish Nuclear Power Inspectorate.
The present workshop, although having a similar scope, is separate from the series of specialists
meetings on In-Core Instrumentation and Reactor Core Assessment. The main objective was to discuss
how instrumentation, methods and models used in core monitoring could be validated, or, if needed,
improved and further developed to provide more reliable and/or detailed information on local power in
the core and on other parameters indirectly affecting fuel duty as, e.g. the core decay ratio in a BWR.
Another important objective was to show how the core monitoring system can be used to support
reactor operation in normal and anticipated transient modes and to supply data used to derive initial
key core parameters for transient and accident analysis.
Although the present methodology is adequate, it has some shortcomings when applied to more
advanced fuel and core designs. Several possible improvements were also mentioned that would lead
to smaller uncertainties in design and to better known uncertainties and margins in operation. Many of
these improvements are based on having better models for fuel and core calculations.
These proceedings present the motivation for holding the workshop. Included are summaries of
the discussions held, the papers presented in the different sessions and some conclusions.
This text is published under the responsibility of the Secretary-General of the OECD. The views
expressed do not necessarily correspond to those of the national authorities concerned.
3

TABLE OF CONTENTS
FOREWORD.................................................................................................................................... 3
EXECUTIVE SUMMARY.............................................................................................................. 9
Annex 1 –On-Line Core Monitoring for BWR, PWR Overview and Comments
on Operation Experience and Further Development................................................ 13
Annex 2 –Technical Programme............................................................................................... 21
SESSION I Requirements on Core Monitoring Systems........................................................ 23
Chair: O. Sandervåg
Ø. Berg, T. Bodal, A. Hornæs, J. Porsmyr
User Interface Design and System Integration Aspects of Core
Monitoring Systems.................................................................................................. 25
T. Andersson
Functional Requirements for Core Surveillance Systems........................................ 37
J.J. Casal
Uncertainty Assessment in BWR Core Monitoring.................................................. 49
SESSION II Sensors, Signal Processing and Evaluation.......................................................... 63
Chairs: E. Saji and Ö. Berg
J.L. Mourlevat, D. Janvier, H.D. Warren
Industrial Tests of Rhodium Self-Powered Detectors: The Golfech 2
Experimentation........................................................................................................ 65
F. Adorján, S. Patai Szabó, I. Pós
Statistical Analysis of the Ratio of Measured and Predicted Rh SPND
Signals in a VVER-440/213 Reactor........................................................................ 79
A. Fukao, E. Saji
The Study on the BWR In-Core Detector Response Calculation............................. 87
T. Kakuta, K. Suzuki, H. Yamagishi, H. Itoh, M. Urakami
Demonstration of Optical In-Core Monitoring System for Advanced
Nuclear Power Reactors........................................................................................... 95
5
J. Runkel, D. Stegemann, J. Fiedler, P. Heidemann, R. Blaser, F. Schmid,
M. Trobitz, L. Hirsch, K. Thoma
New Technologies for Acceleration and Vibration Measurements Inside
Operating Nuclear Power Reactors........................................................................... 103
K. Inagaki, H. Shinohara, S. Yasue, M. Tamuro
Development of Advanced Digital Rod Position Indication System........................ 117
R.J. Cacciapouti, J.P. Gorski
Experience with Fixed Platinum In-Core Detectors................................................. 125
SESSION III Improved Core Models in Core Monitoring........................................................ 133
Chairs: A. Wells and T. Lefvert
H. Moon, A. Wells
Impact of Advanced BWR Core Physics Method on BWR Core Monitoring......... 135
A.O. Noël, L.J. Covington, A. Nilsson, D. Greiner
Core Monitoring Based on Advanced Nodal Methods: Experience and
Plans for Further Improvements and Development.................................................. 147
P. Claesson
JEF-2 Cross-Section Library for CASMO-4: Impact on Core Monitoring
of OKG Reactors...................................................................................................... 163
T. Smed, P. Lansåker, P. Hänggi
BWR Core Stability Prediction On-Line with the Computer Code MATSTAB...... 173
M. Tsuiki, S. Hval
VNEM: Variational Nodal Expansion Method for Light Water Reactor
Core Analysis............................................................................................................ 183
SESSION IV Improved Core Monitoring Systems, Design and Operating Experience......... 193
Chairs: Y. Shimazu and S. Andersson
M. Pecka, J. Svarny, J. Kment
Some Aspects of the New Core Monitoring System at NPP Dukovany
and First Experience................................................................................................. 195
M. Antila, J. Kuusisto
Recent Improvements in On-Line Core Supervision at Loviisa NPP....................... 209
I. Endrizzi, M. Beczkowiak, G. Meier
Refinement of Siemens Core Monitoring Based on Aeroball and PDD
In-Core Measuring Systems Using POWERTRAXTM............................................. 223
Y. Shimazu, M. Masuda
Review of the Current Status of Core Monitoring Systems and the Future
Trend in PWRs in Japan........................................................................................... 235
6
S. Lundberg, J. Wenisch, W. van Teeffelen
Core Supervision Methods and Future Improvements of the Core
MASTER/PRESTO System at KKB........................................................................ 243
H. Potstada, M. Beczkowiak, M. Frank, K. Linnenfelser
The Siemens Advanced Core Monitoring System FNR-K in KKI-1,
KKP-1 and KKK....................................................................................................... 259
J. Eriksson, P. Kelfve, C-Å. Jonsson, S. Andersson
Design and Validation of the New ABB Core Monitoring System.......................... 263
E.K. Lee, Y.H. Kim, K.H. Cha, M.G. Park
Introduction of Virtual Detectors for Core Monitoring System of Korean
Standard Nuclear Power Plant.................................................................................. 273
LIST OF PARTICIPANTS............................................................................................................. 283
7