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Radioactive Flow Characterization for Real-Time Detection

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Radioactive Flow Characterization for Real-Time Detection RADIOACTIVE FLOW CHARACTERIZATION FOR REAL-TIME DETECTION SYSTEMS IN UREX+ NUCLEAR FUEL REPROCESSING A Thesis by THOMAS RUSSELL HOGELIN Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE December 2010 Major Subject: Nuclear Engineering RADIOACTIVE FLOW CHARACTERIZATION FOR REAL-TIME DETECTION SYSTEMS IN UREX+ NUCLEAR FUEL REPROCESSING A Thesis by THOMAS RUSSELL HOGELIN Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE Approved by: Chair of Committee, Sean M. McDeavitt Committee Members, William Charlton Miladin Radovic Head of Department, Raymond Juzaitis December 2010 Major Subject: Nuclear Engineering iii ABSTRACT Radioactive Flow Characterization for Real-Time Detection Systems in UREX+ Nuclear Fuel Reprocessing. (December 2010) Thomas Russell Hogelin, B.M.E., Auburn University Chair of Advisory Committee: Dr. Sean M. McDeavitt The reprocessing of used nuclear fuel requires the dissolution and separation of numerous radioisotopes that are present as fission products in the fuel. The leading technology option in the U.S. for reprocessing is a sequence of processing methods known as UREX+ (Uranium Extraction+). However, an industrial scale facility implementing this separation procedure will require the establishment of safeguards and security systems to ensure the protection of the separated materials. A number of technologies have been developed for meeting the measurement demands for such a facility. This project focuses on the design of a gamma detection system for taking measurements of the flow streams of such a reprocessing facility. An experimental apparatus was constructed capable of pumping water spiked with soluble radioisotopes under various flow conditions through a stainless steel coil around a sodium iodide (NaI) detector system. Experiments were conducted to characterize the impact of flow rate, pipe air voids, geometry, and radioactivity dilution level on activity measurements and gamma energy spectra. Two coil geometries were iv used for these experiments, using 0.5 in stainless steel pipe wound into a coil with a 6 inch diameter; the first coil was 5.5 revolutions tall and the second coil was 9.5 revolutions tall. The isotopes dissolved in the flowing water were produced at the Texas A&M Nuclear Science Center via neutron activation of chromium, gold, cerium, and ytterbium nitrate salts. After activation, the salts were dissolved in distilled water and inserted into the radioactive flow assembly for quantitative measurements. Flow rate variations from 100 to 2000 ml/min were used and activity dilution levels for the experiments conducted were between 0.02 and 1.6 µCi/liter. Detection of system transients was observed to improve with decreasing flow rate. The detection limits observed for this system were 0.02 µCi/liter over background, 0.5% total activity change in a pre-spiked system, and a dilution change of 2% of the coil volume. MCNP (Monte Carlo N-Particle Transport) models were constructed to simulate the results and were used to extend the results to other geometries and piping materials as well as simulate actual UREX stream material in the system. The stainless steel piping for the flow around the detector was found to attenuate key identifying gamma peaks on the low end of the energy spectrum. For the proposed schedule 40 stainless steel pipe for an actual reprocessing facility, gamma rays below 100 keV in energy would be reduced to less than half their initial intensities. The exact ideal detection set up is largely activity and flow stream dependant. However, the characteristics best suited for flow stream detection are: 1) minimize volume around detector, 2) low flow rate for long count times, and 3) low attenuation piping material such as glass. v ACKNOWLEDGEMENTS I would first like to thank my committee chair Dr. Sean McDeavitt for his support and advice through this process. I would like to thank Braden Goddard whose work tied in directly with mine and who assisted me in my own work. I would like to thank the personnel at the Texas A&M Nuclear Science Center for supplying all the radioactive isotopes used in these experiments. I would like to thank Claudio Gariazzo for his assistance with the set up and calibration of my detector system. I would also like to thank the FCML personnel who assisted me in the construction of my experimental apparatus. vi NOMENCLATURE AFCI Advanced Fuel Cycle Initiative CCD-PEG Chlorinated Cobalt Dicarbollide-Polyethylene Glycol FPEX Fission Product Extraction HKED Hybrid K-Edge/X-ray Fluorescence Densitometry HPGe High Purity Germanium HRGS High Resolution Gamma Spectroscopy ICP-MS Inductively Coupled Plasma Mass Spectrometry IDGS Isotope Dilution Gamma-ray Spectrometry IDMS Isotope Dilution Mass Spectrometry KED K-Edge Denitometry KMP Key Measurement Point LSDS Lead Slowing-Down Spectroscopy LWR Light Water Reactor MBA Material Balance Area MCA Multi-Channel Analyzer MCNP Monte Carlo N Particle MIP Multi-Isotope Process MOX Mixed Oxide fuel NaI Sodium Iodide NRC Nuclear Regulatory Commission NRF Nuclear Resonance Fluorescence NSC Nuclear Science Center ORIGEN Oak Ridge Isotope Generation and Depletion Code PUREX Plutonium-Uranium Extraction SEID Standard Error of the Inventory Difference TALSPEAK Trivalent Actinide Lanthanide Separations by Phosphorus- Reagent Extraction from Aqueous Complexes vii TARIS Thermal Atomization Resonance Ionization Spectroscopy TBP Tributyl Phosphate TIMS Thermal Ionization Mass Spectrometry TMFD Tensioned Metastable Fluid Detector TRU Transuranic TRUEX Transuranic Extraction UREX Uranium Extraction XRF X-Ray Fluorescence Elements Am Americium Au Gold Ba Barium Ce Cerium Cm Curium Cr Chromium Cs Cesium Pu Plutonium Rb Rubidium Sr Strontium Tc Technetium U Uranium Yb Ytterbium viii TABLE OF CONTENTS Page ABSTRACT .............................................................................................................. iii ACKNOWLEDGEMENTS ...................................................................................... v NOMENCLATURE .................................................................................................. vi TABLE OF CONTENTS .......................................................................................... viii LIST OF FIGURES ................................................................................................... x LIST OF TABLES .................................................................................................... xiii 1. INTRODUCTION ............................................................................................... 1 2. PREVIOUS WORK ............................................................................................ 6 2.1 Measurement Strategies ....................................................................... 6 2.2 Measurement Technologies .................................................................. 12 3. EXPERIMENT SETUP AND PROCEDURES .................................................. 19 3.1 Selection of Isotopes ............................................................................... 19 3.2 Experimental Apparatus .......................................................................... 21 3.3 Initial Experiments .................................................................................. 26 3.4 Geometry Comparison Experiments ....................................................... 30 3.5 MCNP Simulations ................................................................................. 33 4. RESULTS ............................................................................................................ 36 4.1 Isotope Selection Experiments ............................................................. 37 4.2 Geometry Comparison Experiments .................................................... 50 4.3 MCNP Simulations .............................................................................. 61 5. DISCUSSION ....................................................................................................... 69 6. CONCLUSIONS ................................................................................................... 77 REFERENCES .......................................................................................................... 80 ix Page APPENDIX A ........................................................................................................... 84 APPENDIX B ........................................................................................................... 94 APPENDIX C ........................................................................................................... 96 APPENDIX D ........................................................................................................... 109 VITA ......................................................................................................................... 115 x LIST OF FIGURES FIGURE Page 1 Simplified flow diagram for UREX+1a process ........................................ 4 2 Safeguards Strategy for Rokkasho Reprocessing Plant ............................. 8 3 MBAs and KMPs for UREX+1a facility identified by Feener .................. 10 4 UREX+1a key measurement points required for near real time materials accountancy. ..............................................................................................
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