ORNL/TM-2010/44 SCALE 5.1 Predictions of PWR Spent Nuclear Fuel Isotopic Compositions March 2010 Prepared by G. Radulescu I. C. Gauld G. Ilas DOCUMENT AVAILABILITY Reports produced after January 1, 1996, are generally available free via the U.S. Department of Energy (DOE) Information Bridge: Web site: http://www.osti.gov/bridge Reports produced before January 1, 1996, may be purchased by members of the public from the following source: National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Telephone: 703-605-6000 (1-800-553-6847) TDD: 703-487-4639 Fax: 703-605-6900 E-mail: [email protected] Web site: http://www.ntis.gov/support/ordernowabout.htm Reports are available to DOE employees, DOE contractors, Energy Technology Data Exchange (ETDE) representatives, and International Nuclear Information System (INIS) representatives from the following source: Office of Scientific and Technical Information P.O. 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The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. ORNL/TM-2010/44 Nuclear Science and Technology Division SCALE 5.1 Predictions of PWR Spent Nuclear Fuel Isotopic Compositions G. Radulescu I. C. Gauld G. Ilas Date Published: March 2010 Prepared by OAK RIDGE NATIONAL LABORATORY P.O. Box 2008 Oak Ridge, Tennessee 37831-6283 managed by UT-BATTELLE, LLC for the U.S. DEPARTMENT OF ENERGY under contract DE-AC05-00OR22725 CONTENTS Page LIST OF FIGURES ...................................................................................................................................... v LIST OF TABLES ....................................................................................................................................... ix ACRONYMS ............................................................................................................................................. xiii 1 PURPOSE ............................................................................................................................................. 1 2 QUALITY ASSURANCE REQUIREMENTS .................................................................................... 3 3 USE OF SOFTWARE .......................................................................................................................... 5 3.1 STANDARDIZED COMPUTER ANALYSIS FOR LICENSING EVALUATION (SCALE) CODE SYSTEM ......................................................................................................... 5 3.2 EXCEL ........................................................................................................................................ 5 4 INPUT DATA ....................................................................................................................................... 7 5 ASSUMPTIONS ................................................................................................................................... 9 5.1 INITIAL URANIUM ISOTOPIC CONTENTS ......................................................................... 9 5.2 MODERATOR TEMPERATURE AND DENSITY .................................................................. 9 5.3 EFFECTIVE FUEL TEMPERATURE..................................................................................... 10 5.4 BORON LETDOWN CURVE ................................................................................................. 10 6 EXPERIMENTAL PROGRAMS AND DATA ................................................................................. 11 6.1 SELECTION OF SPENT FUEL ISOTOPIC COMPOSITION DATA ................................... 11 6.2 SUMMARY OF DATA USED IN PREVIOUS YMP ANALYSES ....................................... 11 6.3 REVIEW OF RADIOCHEMICAL ANALYSIS DATA .......................................................... 13 6.4 DATA QUALIFICATION ....................................................................................................... 16 6.5 EXPERIMENTAL DATA ANALYSIS ................................................................................... 17 6.6 NUCLEAR DATA .................................................................................................................... 19 6.7 ANALYTICAL MEASUREMENT UNCERTAINTIES ......................................................... 21 7 EXPERIMENTAL DATA .................................................................................................................. 23 7.1 TRINO VERCELLESE ............................................................................................................ 23 7.2 OBRIGHEIM (KWO) ............................................................................................................... 31 7.2.1 Karlsruhe Reprocessing Plant (WAK) ......................................................................... 31 7.2.2 JRC Research Program ................................................................................................ 33 7.3 TURKEY POINT UNIT 3 ........................................................................................................ 40 7.4 H. B. ROBINSON UNIT 2 ....................................................................................................... 42 7.5 CALVERT CLIFFS UNIT 1 ..................................................................................................... 45 7.5.1 PNL Measurements ...................................................................................................... 46 7.5.2 KRI Measurements ...................................................................................................... 47 7.5.3 103-MLA098 ............................................................................................................... 49 7.5.4 104-MKP109 ................................................................................................................ 50 7.5.5 106-NBD107 ................................................................................................................ 51 7.6 TAKAHAMA UNIT 3 .............................................................................................................. 55 7.7 TMI UNIT I .............................................................................................................................. 61 7.7.1 ANL Measurements ..................................................................................................... 62 7.7.2 GE-VNC Measurements .............................................................................................. 66 7.8 GÖSGEN REACTOR: ARIANE PROGRAM ......................................................................... 69 7.9 GKN UNIT II ............................................................................................................................ 74 7.10 GÖSGEN REACTOR: MALIBU PROGRAM ........................................................................ 75 iii CONTENTS (continued) Page 8 ASSEMBLY DESIGN AND IRRADIATION HISTORY DATA ..................................................... 79 8.1 TRINO VERCELLESE ............................................................................................................ 79 8.2 OBRIGHEIM ............................................................................................................................ 88 8.3 TURKEY POINT UNIT 3 ........................................................................................................ 95 8.4 H. B. ROBINSON UNIT 2 ....................................................................................................... 99 8.5 CALVERT CLIFFS UNIT 1 ................................................................................................... 105 8.6 TAKAHAMA UNIT 3 ............................................................................................................ 116 8.7 TMI UNIT 1 ............................................................................................................................ 121 8.8 GÖSGEN: ARIANE PROGRAM .......................................................................................... 131 8.9 GKN II .................................................................................................................................... 136 8.10 GÖSGEN: MALIBU PROGRAM .......................................................................................... 140 9 SCALE TWO-DIMENSIONAL DEPLETION CALCULATION METHOD ................................. 141 9.1 METHOD DESCRIPTION ..................................................................................................... 141 9.2 MODELING APPROACH ....................................................................................................