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VVER Reactor Fuel Performance, Modelling and Experimental Support BG9600388 VVER Reactor Fuel Performance, Modelling and Experimental Support Proceedings of an international seminar, heidin St. Constantine, Varna, Bulgaria, on? - 11 November 1994 Compiled and edited by S. Stefanova, P. Chantoin and I. G. Kolev Bulgarian Academy of Sciences Institute for Nuclear Research and Nuclear Energy VVER Reactor Fuel Performance, Modelling and Experimental Support Proceedings of an international seminar, held in St. Constantine, Varna, Bulgaria, on 7-11 November 1994 Compiled and edited by Svetlana Stefanova, Pier Chantoin and Ivan G. Kolev Executive Editor: Ivan G. Kolev Technical Editor: Albena Mladenova Computer Processing: Albena Mladenova and Lidia Kinova ISBN 954-90025-2-7 © Institute for Nuclear Research and Nuclear Energy, 1995 All rights reserved. Except for copying for conventional scientific purposes, no part of this publication may be reproduced or transmitted in any form without the prior written permission of the publisher. Papers included in this compilation are published on the understanding that the authors of the contributions are fully responcible for the opinions expressed in the corresponding papers and that their publication does not necessarily reflect the views of the publisher or any other institution supporting this publication. Published by the Institute for Nuclear Research and Nuclear Energy of the Bulgarian Academy of Sciences, Tsarigradsko shousse 72, Sofia 1784, Bulgaria Printed by Evtimov-llinda ET, Tzar Boris III Blvd., bl. 59, Sofia 1612, Bulgaria Printed in Bulgaria Table of Contents From the Editors 5 Organising Committee, Secretariat and Supporting Institutions of the Seminar 6 List of Seminar Participants 7 Part 1. VVER Fuel Performance and Economics: Status and Improvement Prospects VVER Fuel Performance and Economics: Status and Improvement Prospects. Panel Discussion Report. Yu. Bibilashvili, L Goldstein 11 Nuclear Fuel Utilization in Kozloduy NPP. Z Boyadjiev, Ts. Haralampieva, Ts. Peychinov 13 The Evolution of the Fuel Cycle at the Dukovany NPP. J. Bajgl. 27 Practical Experience with the Fuel Monitoring at Ducovany NPP. J. Kment, R. Svoboda, M. Valach 29 VVER Fuel Performance, Development, QA and Future Prospects at Loviisa NPS. P. L6s6nen 33 State-of-the-Art and Perspectives of the Fuel Rod and Material Development Activities in Russia. Yu. Bibilashvili 39 Operational Indices of VVER-1000 Fuel Assemblies and Their Improvements. /. Vasilchenko, E. Demin 49 Status and Prospects of VVER In-Core Fuel Management Activities. A. Novikov, V. Pavlov, A. Pavlovichev, V. Proselkov, V. Saprykin 53 Status and Prospects of Activities on Algorithms and Methods in VVER-1000 Core Control. P. Filimonov, Y. Krainov, V. Proselkov 59 Improvement of Operation Efficiency for VVER-440 and VVER-1000 from TRIGON Fuel Assembly Design Features. A. Silberstein 67 The International VVER Fuels Market. J.E. Gingold, L Goldstein, A.A Strasser 75 Part 2. VVER Fuel Behaviour Modelling and Experimental Support VVER Fuel Behaviour Modelling and Experimental Support. Panel Discussion Report. Yu. Bibilashvili, K. Lassmann 83 Main Concepts and Objectives of Fuel Performance Modelling and Code Development. K. Lassmann, C. O'Carroll, J. vandeLaar, I. Ray, S. Stefanova, P. Chantoin 85 TRANSURANUS: A Fuel Rod Analysis Code Ready for Use. K. Lassmann, C. O'Carroll, J. vandeLaar, C. Ott. 95 Overview of Fuel Testing Capabilities at the OECD Halden Reactor Project. W. Wiesenack 103 Assesment of VVER Fuel Condition in Design Basis Accident. Yu. Bibilashvily, N. Sokolov, L Andreeva-Andrievskaya, Yu. Vlasov, O. Nechaeva, A. Salatov 109 Influence of Fuel-Cladding System Deviations from the Model of Continuous Cylinders on the Parameters of VVER Fuel Element Working Ability. A. Scheglov 115 Application of the Modified Version of SPPS-1 - HEXAB-2DB Computer Code System for the Operational Analyses of Fuel Behaviour in VVER-440 Reactor Cores at Kozloduy NPP. Ts. Haralampieva, I. Stoyanova, A. Antov, T. Simeonov, P. Petkov 119 Results of Calculation of VVER-440 Fuel Rods (Kolskaya-3 NPP) at High Burnup. A. Scheglov, V. Proselkov, M. Panin, Y. Pytkin, V. Tzibulya 131 Analysis of VVER-440 Fuel Performance Under Normal Operating Conditions. 0. Gunduz, S. KOse, T. Akbas, 0. Qolak 137 Experimental Support of VVER-440 Fuel Reliability and Serviceability at High Burnup. A. Smirnov, V. Ivanov, A. Pnyushkin, V. Tsibulya, V. Kolosovsky, Yu. Bibilashvili, K. Dubrovin 141 VVER-440 Fuel Rod Performance Analysis with PIN-Micro and TRANSURANUS Codes. M. Vitkova, M. Manolova, S. Stefanova, V. Simeonova, G. Passage, Ts. Haralampieva, K. Lassmann 147 FUMEX Cases 1, 2, and 3 Calculated Pre-Test and Post-Test Results. S. Stefanova, M. Vitkova, G. Passage, M. Manolova, V. Simeonova, A. Scheglov, V. Proselkov, Ts. Haralampieva 153 Modeling of VVER-1000 Fuel: State and Prospects. A. Medvedev, Yu. Bibilashvili, S. Bogatyr, G. Hvostov 163 Main Examination Results of VVER-1000 Fuel After Its Irradiation in Power Reactors. Yu. Bibilashvily, K. Dubrovin, I. Vasilchenko, A. Yenin, A. Kushmanov, A. Smirnov, V.Smirnov 173 First Qualitative Analysis of Fuel Irradiation Results Carried Out in the MR Reactor on VVER-1000 Fuel. P. Chantoin, K. Dubrovin, P. Platonov, V. Onufriev 179 Part 3. Licensing of VVER Fuel and Fuel Analysis Codes Licensing of VVER Fuel and Fuel Analysis Codes. Panel Discussion Report. P. Chantoin 187 Nuclear Fuel Licensing Procedures in Bulgaria. Y. Harizanov 189 Nuclear Regulatory Guides for LWR (PWR) Fuel in Japan and Some Related Safety Research. M. Ichikawa ....191 Practice and Trends in Nuclear Fuel Licensing in France (Pressurized Water Reactor Fuels). S. Roudier, D. Bade!, R. Beraha, M. Champ, N. Tricot, P. TranDai 201 Fuel Utilization Experience in Bohunice NPP and Regulatory Requirements for Implementation of Progressive Fuel Management Strategies. V. Petenyi, P. Darllek, J. Majercfk 205 Part 4. Spent Fuel of VVER Plants Spent Fuel of VVER Plants. Panel Discussion Report. F. Berge, E Vapirev 211 A Strategic Approach to Short- and Long-Term Irradiated VVER Fuel Management. P. Wilcox,'T. M. Conboy 213 Spent Fuel Generated by the Kozloduy Nuclear Power Plant within the Period 1974 -1994. P.Peev 215 Status and Operational Experience Report of Spent Fuel Storage Facility in Kozloduy NPP for the Period 1990-1994. N. Kalimanov 217 Storage of Spent Nuclear Fuel: The Problem of Spent Nuclear Fuel in Bulgaria. Z Boyadjiev, E. I. Vapirev 219 Spent Fuel Disposal Problem in Bulgaria. M. Milanov, I. Stefanova 223 VVER Spent Fuel Storage. C. C. Bower, C. Lettington 229 Key Technical Issues Relating to the Safety of Spent Fuel Dry Storage in Vaults: CASCAD System. F. Berge 237 Conversion of Highly Enriched Uranium in Thorium-232 Based Oxide Fuel for Light Water Reactors: MOX-TFuel. E.I. Vapirev, T. Jordanov, I. Christoskov 241 Supplement VVER Fuel Literature Review. Collection of abstracts of VVER fuel data at manufacturing, reactor operation, experiment, post-irradiation examination and pool-side inspection. S. Stefanova, M. Manolova, M. Vitkova, V. Simeonova, G. Passage, P. Chantoin 247 Advertising Index INRNE General Profile 10 INRNE Applied Research in Nuclear Engineering 82 EQE Bulgaria Ltd 186 DECOM - SOFIA Co. Ltd 208 INRNE Radiochemistry and Radioecology Studies 210 4 From the Editors This publication is a compilation of papers presented at the International Seminar on VVER Reactor Fuel Performance, Modelling and Experimental Support, organised by the Institute for Nuclear Research and Nuclear Energy of the Bulgarian Academy of Sciences in co-operation with the International Atomic Energy Agency. The Seminar took place in F.J. Curie International House of Scientists at the St. Constantine resort near Varna, Bulgaria, from 7 to 11 November 1994 and was attended by 70 specialists from 16 countries, including representatives of all major Russian plants and institutions responsible for VVER reactor fuel manufacturing, design and research. The Seminar was divided into 6 sessions, covering (1) actual performance of VVER reactor fuel, (2) trends for improved fuel utilisation by introduction of new fuel design and management, (3) fuel economics and licensing, (4) fuel behaviour analysis and corresponding computer codes, (5) experimental support of fuel modelling and (6) problems of spent nuclear fuel of VVER plants - that is, most of VVER fuel life-cycle stages. Four panel discussion sessions were organised and corresponding reports are also included in this publication. During compilation and editing, all papers have been divided into 4 sections, corresponding to panel discussion sessions, and papers have been re-ordered and grouped according to their main topics for convinience and to facilitate information retrieval. In addition, a comprehensive collection of abstracts of published bibliographic sources of VVER fuel data is included in the Supplement. In certain cases, the text and captions have been sligthly edited for languige and uniformity reasons. The information contained is, however, in responcibility of the listed authors and neither the seminar organisers, the Publisher, nor any of the institutions supporting the seminar, hold any responsibility for the use of the information contained in the named articles. The Editors express their gratitude to those authors who presented the text and graphics of their contributions in convenient computer files, as well as to the INRNE staff, responsible for the computer processing of this publication, especially to Ms. Albena Mladenova and to Ms. Lidia Kinova. Finally, this
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