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NUREG/CR-7162 "Analysis of Experimental Data for High Burnup BWR Spent Fuel Isotopic Validation

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NUREG/CR-7162 NUREG/CR-7162 ORNL/TM-2013/18 Analysis of Experimental Data for High Burnup BWR Spent Fuel Isotopic Validation – SVEA-96 and GE14 Assembly Designs Office of Nuclear Regulatory Research AVAILABILITY OF REFERENCE MATERIALS IN NRC PUBLICATIONS NRC Reference Material Non-NRC Reference Material As of November 1999, you may electronically access Documents available from public and special technical NUREG-series publications and other NRC records at libraries include all open literature items, such as books, NRC’s Public Electronic Reading Room at journal articles, transactions, Federal Register notices, http://www.nrc.gov/reading-rm.html. Publicly released Federal and State legislation, and congressional reports. records include, to name a few, NUREG-series Such documents as theses, dissertations, foreign reports publications; Federal Register notices; applicant, and translations, and non-NRC conference proceedings licensee, and vendor documents and correspondence; may be purchased from their sponsoring organization. NRC correspondence and internal memoranda; bulletins and information notices; inspection and investigative Copies of industry codes and standards used in a reports; licensee event reports; and Commission papers substantive manner in the NRC regulatory process are and their attachments. maintained at— The NRC Technical Library NRC publications in the NUREG series, NRC Two White Flint North regulations, and Title 10, “Energy,” in the Code of 11545 Rockville Pike Federal Regulations may also be purchased from one Rockville, MD 20852–2738 of these two sources. 1. The Superintendent of Documents These standards are available in the library for reference U.S. Government Printing Office Mail Stop SSOP use by the public. Codes and standards are usually Washington, DC 20402–0001 copyrighted and may be purchased from the originating Internet: bookstore.gpo.gov organization or, if they are American National Standards, Telephone: 202-512-1800 from— Fax: 202-512-2250 American National Standards Institute nd 2. The National Technical Information Service 11 West 42 Street Springfield, VA 22161–0002 New York, NY 10036–8002 www.ntis.gov www.ansi.org 1–800–553–6847 or, locally, 703–605–6000 212–642–4900 A single copy of each NRC draft report for comment is available free, to the extent of supply, upon written Legally binding regulatory requirements are stated request as follows: only in laws; NRC regulations; licenses, including Address: U.S. Nuclear Regulatory Commission technical specifications; or orders, not in NUREG- Office of Administration series publications. The views expressed in Publications Branch contractor-prepared publications in this series are Washington, DC 20555-0001 not necessarily those of the NRC. E-mail: [email protected] Facsimile: 301–415–2289 The NUREG series comprises (1) technical and administrative reports and books prepared by the Some publications in the NUREG series that are staff (NUREG–XXXX) or agency contractors posted at NRC’s Web site address (NUREG/CR–XXXX), (2) proceedings of http://www.nrc.gov/reading-rm/doc-collections/nuregs conferences (NUREG/CP–XXXX), (3) reports are updated periodically and may differ from the last resulting from international agreements printed version. Although references to material found on (NUREG/IA–XXXX), (4) brochures (NUREG/BR– a Web site bear the date the material was accessed, the XXXX), and (5) compilations of legal decisions and material available on the date cited may subsequently be orders of the Commission and Atomic and Safety removed from the site. Licensing Boards and of Directors’ decisions under Section 2.206 of NRC’s regulations (NUREG–0750). DISCLAIMER: This report was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any employee, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party’s use, or the results of such use, of any information, apparatus, product, or process disclosed in this publication, or represents that its use by such third party would not infringe privately owned rights. NUREG/CR-7162 ORNL/TM-2013/18 Analysis of Experimental Data for High Burnup BWR Spent Fuel Isotopic Validation – SVEA-96 and GE14 Assembly Designs Manuscript Completed: December 2012 Date Published: March 2013 Prepared by: H. J. Smith I. C. Gauld U. Mertyurek Oak Ridge National Laboratory Managed by UT-Battelle, LLC Oak Ridge, TN 37831-6170 Mourad Aissa, NRC Project Manager NRC Job Code N6540 Office of Nuclear Regulatory Research ABSTRACT This report describes experimental radiochemical assay data, recently acquired under two international collaboration programs, for the isotopic compositions in high burnup spent nuclear fuel from modern boiling water reactor (BWR) assemblies. The Belgian MALIBU extension program provides measured data for isotopic contents of more than 50 nuclides in spent fuel samples selected from a SVEA-96 (10×10) Optima fuel assembly with burnups between 59 and 63 GWd/MTU. An experimental program in Spain provides additional isotopic data for more than 60 nuclides in samples selected from a GE14 (10×10) fuel assembly that cover a burnup range 38 to 56 GWd/MTU. These samples were selected from different axial elevations of a fuel rod, representing therefore a wide range of moderator void conditions. The measurement data include concentrations of actinides and fission products important to nuclear decay heat, radiological sources, and nuclear criticality safety. These data are essential for validation of the computational models used to calculate fuel isotopic concentrations and activities applied in reactor and spent nuclear fuel safety studies. Computational benchmark analyses using the measurements are performed with the TRITON two-dimensional depletion sequence in the SCALE 6.1 computer code system and ENDF/B-VII-based nuclear data libraries. These measurements represent an important contribution to the code benchmark database by providing data for modern BWR assembly designs and operating conditions representative of currently operating reactors. iii CONTENTS Page ABSTRACT ................................................................................................................................................. iii LIST OF FIGURES .................................................................................................................................... vii LIST OF TABLES ....................................................................................................................................... ix ACKNOWLEDGMENTS ........................................................................................................................... xi LIST OF ACRONYMS AND UNITS ....................................................................................................... xiii 1. INTRODUCTION ................................................................................................................................ 1 2. EXPERIMENTAL PROGRAMS ......................................................................................................... 5 2.1 MALIBU EXTENSION PROGRAM ........................................................................................ 5 2.1.1 Leibstadt SVEA-96 Samples ........................................................................................ 5 2.1.2 Measurements ............................................................................................................... 8 2.2 ENUSA PROGRAM ................................................................................................................ 14 2.2.1 Forsmark 3 GE14 Samples ......................................................................................... 14 2.2.2 Measurements ............................................................................................................. 14 3. ASSEMBLY DESIGN AND MODELING DESCRIPTION ............................................................. 19 3.1 COMPUTATIONAL METHODS AND NUCLEAR DATA .................................................. 19 3.2 SVEA-96 OPTIMA ASSEMBLY ............................................................................................ 20 3.2.1 Description ................................................................................................................. 20 3.2.2 Assembly Model ........................................................................................................ 23 3.3 GE14 ASSEMBLY ................................................................................................................... 25 3.3.1 Description ................................................................................................................. 25 3.3.2 GE14 Assembly Model .............................................................................................. 29 4. RESULTS ........................................................................................................................................... 33 4.1 LEIBSTADT SVEA-96 SAMPLES ......................................................................................... 34 4.1.1 KLU1 .......................................................................................................................... 34 4.2 FORSMARK GE14 SAMPLES ............................................................................................... 38 4.2.1 Burnup Monitor Isotopes...........................................................................................
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