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C D NE a International Workshop on Boiling Wate R Reactor Stability

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C D NE a International Workshop on Boiling Wate R Reactor Stability CSNI Report 178 General Distribution C D NE A International Workshop on Boiling Wate r Reactor Stability Proceedings Sponsored by the Nuclear Energy Agency of the Organisation for Economic Cooperation and Development With the support of the United States Nuclear Regulatory Commission an d Brookhaven National Laboratory Day's Hotel-Brookhaven Holtsville, New York 17th-19th October 1990 COMMITTEE ON THE SAFETY OF NUCLEAR INSTALLATIONS OECD NUCLEAR ENERGY AGENCY 38, boulevard Suchet, 75016 Paris, Franc e International Workshop on Boiling Water Reactor Stability Proceedings Sponsored by the Nuclear Energy Agency of the Organisation for Economic Cooperation and Developmen t With the support of the United States Nuclear Regulatory Commission an d Brookhaven National Laboratory Day's Hotel-Brookhaven Holtsville, New York 17th-19th October 1990 31379 Foreword General design criteria for nuclear power plants in every OECD country require that the reactor core and associated coolant, control, and protection systems be designed so that power oscillations which can result in conditions exceeding acceptable fuel design limits are not possible, or they can be reliably and readily detected and suppressed. In practice, this means that reactor cores should be stable with regard to perturba- tions from their normal operating state, so that expected variations to the operating parameters do not in- duce undamped power oscillations. These power oscillations can take a variety of forms, from very local power peaks which can cause no damage, or only slight damage to only a few fuel rods, to large core-wide os - cillations where entire segments of the core can become neutronically uncoupled, with wide power power swings. Ever since the fust boiling water reactors began operating, over 30 years ago, it has been recognized that their operation under certain conditions of power and flow could cause power and flow oscillations. Consid- erable research was performed at that time to better understand the principal operating parameters which contribute to the initiation of these oscillations, and guidelines were developed to avoid plant operation under the conditions which were the most unstable. Experiments in the the first Special Power Excursion Reactor Test (SPERT-1) program produced spontaneous power oscillations, and investigations in an out-of- pile loop were necessary to demonstrate that the immediate cause of the oscillations was a power-to-reac- tivity feedback . Further investigations indicated that the instabilities were limited to certain areas on the operating map. These regions could not be absolutely defined, but there was sufficient understanding of them that they could be generally avoided, with only minor examples of instability events . More recently, though, several reactor events, and especially one that occurred at the La Salle Nuclear Power Station in March 1988, have instigated a reexamination of BWR instability characteristics and conse- quences. Discussions began among reactor vendors, BWR owners, and regulatory agencies to explore the phenomena associated with asymmetric oscillations during normal operation, and large oscillations durin g anticipated transient without scram events . These conditions were determined to be the significant areas re- quiring further investigation as a result of the La Salle event, and analysts have continued to explore ways o f improving the tools and knowledge for understanding these situations. The International Workshop on BWR Stability was organized in response to these efforts, in the hope that i t could bring together analysts and researchers from reactor vendors, utilities, and governmental organiza- tions for the purpose of promoting an enhanced international focus on common problems and their resolu- tion. Contents a 3 The Organization for Economic Co-operation and Developmen t ix The Nuclear Energy Agency x The Committee on the Safety of Nuclear Installations xi SESSION 1 THE SAFETY SIGNIFICANCE OF BWR INSTABILIT Y Chairman: R. Caruso (OECD/Nuclear Energy Agency ) 1.1 Resolution of U .S. Regulatory Issues Involving Boiling Water Reactor Stability L Phillips (United States) 3 1.2 Overview of Current BWR Owners Group Stability Program s T. Rausch, H. Pfefferlen (United States) 30 1.3 BWR Core Thermal-Hydraulic Stability: Experience and Safety Significance H. Pfefferlen, R. Rausch, G. Watford (United States) 45 SESSION 2 OBSERVED BWR INSTABILITIES Chairman: W. Frisch (Germany) 2.1 Stability Investigations of Forsmark 1 BWR, During Powe r Ascension after the Annual Shutdown 198 7 B. Andersson, B . G. Bergdahl, J. Blomstrand, P. Landsdker, Th. Lindqvist, J . Lorenzen, R. Oguma, P. Reibe (Sweden) 59 2.2 Flow Stability Investigations of SVEA BWR Fue l J. Blomstrand, R. Eklund, O. Nylund (Sweden) 74 2.3 Practical Experiences with Instability Measurements i n German BWRs and Related Consequence s L. P.Brandes, W. Waschull (Germany, F.R.) 87 2.4 First Stability Tests in a Large BWR with a Complete 9x9 Cor e K. Bauersfeld, R. Fuge, H. Heckermann, It. Seepolt (Germany, ER.) 104 v SESSION 3 INSTABILITY MEASUREMENTS AN D INSTRUMENTATION TO DETECT INSTABILIT Y Chairman: R. Bari (United States) 3.1 Monitoring Local Changes of the Core Stability of a BWR T. Van der Hagen (Netherlands ) 117 3.2 Validation and Implementation of an On-Line Stability Monitor D.Pruitt, L. Nielsen, S. Jones, M. Humphreys, R. Torres (United States) 130 3.3 BWR-Stability Investigation in Ringhals 1 Measurement Data from October 26, 1989 D. G. Bergdahl, R. Oguma (Sweden) 142 SESSION 4A PHENOMENOLOGY OF BWR INSTABILITY SENSITIVITY STUDIE S Chairman: W. Wulff (United States ) 4A.1 3D Analyses of BWR Stability in Low Flow Condition T.Hagt, T. Saitoh, J. Tanji (Japan) 163 4A.2 Examination of Nuclear Thermal Hydrauli c Oscillation Modes in BWR Core T. Anegawa, T. Fukahori, O. Yokomi7o, Y. Yoshimoto, I . Sumida (Japan) 175 4A.3 Fuel Integrity Evaluation at Instability Phenomena T Takeuchi, S . Kasai, H . Namba, Y. Takigawa, S. Ts unoyma (Japan) 190 4A.4 RAMONA-3B and TRAB Assessment using Oscillation Data from T VO I j~ Valtonen (Finland) 205 4A.5 Radial Nodalization Effects on BWR Stability Calculation s J. March-Leuba (United States) 232 4A.6 A Sensitivity Analysis for the BWR Stability Behaviou r S. Langenhuch, K. Schmidt (Germany, F.R.) 241 4A.7 A Parametric Study of Variables Affecting BWR Instabilit y G. Johnsen, S. Rouhani, R . Shumway (United States) 257 SESSION 4B PHENOMENOLOGY OF BWR INSTABILIT Y THEORETICAL STUDIES Chairman: B. Sheron (United States ) 4B.1 Harmonic Modes of the Neutron Diffusion Equation: Application to BWR Stability S. Congdon, C. Martin, D. Salmon, G. Watford, A. Wirth (United States) 273 vi 4B.2 Application of Galerkin's Method for Calculating Boiling Water Reactor Limit-Cycle Amplitude using the LAPUR Feedback-Transfer Function and the Point-Kinetics Equation s B. Damian. J. March-Leuba, J. Euler (United States) 289 4B3 Influence of Bubble Residence Time in BWR Stability J. Ballestrin, J.Blâzqueg (Spain) 301 4B.4 An Elementary Introduction to the Problem of Density Wave Oscillation s K. Svanholm (Norway) and J. Friedly (United States) 317 SESSION 5 VALIDATION OF THE ANALYTICAL TOOLS Chairman: T. Haga (Japan) 5.1 Space-dependent Stability Analysis of Core Wide and Regional Modes in BWR T. Anegawa, S. Ebata, O. Yokomizo, Y. Yoshimoto (Japan) 337 5.2 TRACG Analysis of BWR Plant Stability Data J. Andersen, J. Garrett, J.Shang (United States) 354 5.3 Summary of RETRAN Calculations on LaSalle-2 Neutron Flux Oscillatio n Event Performed at JAER I F. Araya, M. Hirano, A. Kohsaka, K. Matsumoto, M. Yokobayshi, K. Yoshida (Japan) 370 5.4 Assessment and Application of the RAMONA Three-Dimensional Transient Code to BWR Stability S. Katsenelenbogen, L, Moberg (Norway) 385 5.5 RAMONA-3B Calculations of Core-Wide and Regional Power/Flow Oscillations-Comparison with Oskarsham 3 Natural Circulation Test Data S. Andersson, M. Stepniewshi (Sweden) 397 5.6 Assessment of RAMONA-3B Methodology with FRIGG Dynamic Tests U.S. Rohatgi, L.Y. Neymotin, W. Wulff (United States) 412 SESSION 6 CODE APPLICATIONS Chairman: O. Sandervdg (Sweden) 6.1 BWR Core Thermal-Hydraulic Stability in Anticipated Transients without Scram L. Claassen, J. Garrett, T. Rausch (United States) 433 6.2 Analysis of Water Level Reduction during ATWS/Instability Events J Jensen, R. Galer (United States) 446 63 An Analysis of Reactor Transient Response for Boiling Water Reactor ATWS Event s M. Chaiko, P. Hill, E. Jebsen (United States) 457 6.4 Effect of Power Oscillations on Suppression Pool Heating during ATWS Condition s H. Cheng, A. Mallen, W. Wulff (United States) 477 vii 63 Effect of Balance of Plant and Control System Feedback on Amplitude of Power and Flow Oscillations H. Cheng, A. Mallen, W.Wulff (United States) 494 6.6 Causes ofInstability at LaSalle and Consequences from Postulated SCRAM Failure H. Cheng, A. Mallen, W. Wulff (United States) 509 6.7 Investigation of Chinshan BWR/4 Stability Analysi s H. Chou, C. Pan, B. Pei, C. Shih, J-R Wang. R. Yuann (Taiwan) 523 Summary 537 List of Participants 539 OECD In 1948, the United States offered Marshall Plan aid to Europe, provided the war-torn European countries worked together for their own recovery. This they did in the Organisation for European Economic Co- operation (OEEC). In 1960, Europe's fortunes had been restored; her standard of living was higher than ever before. On both sides of the Atlantic the interdependence of the industrialised countries of the Western World was now widely recognised.
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