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VVER-1000 Coolant Transient Benchmark Nuclear Science NEA/NSC/DOC(2002)6 VVER-1000 Coolant Transient Benchmark PHASE 1 (V1000CT-1) Vol. I: Main Coolant Pump (MCP) switching On – Final Specifications Boyan Ivanov and Kostadin Ivanov Nuclear Engineering Program, USA Pavlin Groudev and Malinka Pavlova INRNE, Academy of Sciences, Bulgaria Vasil Hadjiev Nuclear Power Plant Kozloduy, Bulgaria US Department of Energy 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), Korea (12th December 1996) and the Slovak Republic (14 December 2000). 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 28 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, Slovak Republic, 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 2002 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. (33-1) 44 07 47 70, 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, (508)750-8400, 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 The OECD Nuclear Energy Agency (OECD/NEA) has completed under US NRC sponsorship a PWR Main Steam Line Break (MSLB) Benchmark involving thermal-hydraulic/neutron kinetics codes. Recently, another OECD-NRC coupled code benchmark was initiated for a BWR turbine trip (TT) transient. During the course of defining and co-ordinating the OECD-NRC PWR MSLB and BWR TT benchmarks a systematic approach has been established to validate best-estimate coupled codes. This approach employs a multi-level methodology that not only allows for a consistent and comprehensive validation process but also contributes to determine additional requirements and to prepare a basis for licensing application of the coupled calculations for a specific reactor type, i.e. establishing safety expertise in analysing reactivity transients. Professional communities have been established during the course of these benchmark activities that led to in-depth discussions of the different aspects required for assessing neutron kinetics modelling relative to a given reactor, and finally on how to implement best-estimate methodologies for transient analysis using coupled codes. The above examples demonstrate the benefit of establishing such international coupled standard problems for each type of reactor. In the framework of the United States Department of Energy (DOE) International Nuclear Safety Program (INSP), a project was started in 2001 with an overall objective to assess computer codes used in the safety analysis of VVER power plants, specifically for their use in analysing reactivity transients in a VVER-1000 reactor. As a result, a coupled benchmark problem based on data from the Bulgarian Kozloduy Nuclear Power Plant (NPP) has been developed for the purpose of assessing neutron kinetics modelling for a VVER-1000 reactor. This problem is being analysed using both point kinetics and three-dimensional kinetics models. Based on the experience accumulated in safety analyses of western-type reactors (see the examples given above for PWR and BWR international standard benchmark problems), it was proposed that Phase 1 of the VVER-1000 benchmark problem be extended to an international standard problem. During the Starter International VVER-1000 Benchmark Meeting, which took place on 30 May 2002 in Dresden, Germany, this benchmark was proposed and accepted by the participants. It will be labelled as VVER-1000 Coolant Transient Benchmark (V1000CT) and consist of two phases. Phase 1 (V1000CT-1), led by Pennsylvania State University (PSU), is a main coolant pump (MCP) switching on transient when the three other MCPs are in operation. Phase 2 (V1000CT-2), led by the French Commissariat à l’énergie atomique (CEA), includes calculation of coolant mixing experiments and a main steam line break (MSLB) analysis. Both PSU and the CEA are working in co-operation with the Bulgarian Institute for Nuclear Research and Nuclear Energy (INRNE). The sponsors of the benchmark are the OECD/NEA, US DOE, CEA and IRSN. The Kozloduy Nuclear Power Plant (KNPP) provides technical support and the Atomic Energy Research (AER) Working Group D participates in the benchmark activities. This report provides the specifications for the international, coupled VVER-1000 Coolant Transient (V1000CT-1) benchmark problem. The specification report has been prepared jointly by PSU and INRNE in co-operation with leading specialists from KNPP. The work is sponsored by the 3 US DOE, the OECD/NEA, and the Nuclear Engineering Program at PSU, and is being performed with the assistance of Argonne National Laboratory (ANL). The reference MCP switching on problem chosen for simulation in a VVER-1000 is an experiment that was conducted by Bulgarian and Russian engineers during the plant-commissioning phase at the KNPP Unit 6 as part of the start-up tests. The test was carried out due to its importance for the safety of the VVER-1000, model 320 reactor at the NPP. This event is characterised by a rapid increase in coolant flow through the core resulting in a coolant temperature decrease, which is spatially dependent. All necessary information to model and analyse the transient with best-estimate system thermal-hydraulic codes using both point kinetics and three-dimensional kinetics models is provided in the report. A KNPP Unit 6 RELAP5 thermal-hydraulic skeleton input deck, as well as the KNPP 6 RELAP5 four-loop model nodalisation diagram are also provided in Appendix A. They represent part of the source information that provides the plant data. They are derived from the baseline VVER-1000 RELAP5 input deck shown in Appendix D, developed and validated by INRNE for KNNP Unit 6. This baseline input deck is considered part of the data specification. The specification covers the three exercises of Phase 1 and the required output information is specified for each exercise. In addition, a CD-ROM is also being prepared with the transient boundary conditions, decay heat values as a function of time, and cross-section
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