Los Alamos. OF nm LA-"'- Title: HYBRID KED/XRF MEASUREMENT OF MINOR ACTINIDES IN REPROCESSING PLANTS. S. T. Hsue and M. L.

Similar documents
A Few-Group Delayed Neutron Model Based on a Consistent Set of Decay Constants. Joann M. Campbell Gregory D. Spriggs

ION EXCHANGE SEPARATION OF PLUTONIUM AND GALLIUM (1) Resource and Inventory Requirements, (2) Waste, Emissions, and Effluent, and (3) Facility Size

CQNl_" RESPONSE TO 100% INTERNAL QUANTUM EFFICIENCY SILICON PHOTODIODES TO LOW ENERGY ELECTRONS AND IONS

12/16/95-3/15/96 PERIOD MULTI-PARAMETER ON-LINE COAL BULK ANALYSIS. 2, 1. Thermal Neutron Flux in Coal: New Coal Container Geometry

Hsue, M. Collins, and R. Cole DISCLAIMER

Walter P. Lysenko John D. Gilpatrick Martin E. Schulze LINAC '98 XIX INTERNATIONAL CONFERENCE CHICAGO, IL AUGUST 23-28,1998

Hyperon Particle Physics at JHF. R. E. Mischke

Abstract of paper proposed for the American Nuclear Society 1997 Winter Meeting Albuquerque, New Mexico November 16-20, 1997

APPLICATION SINGLE ION ACTIVITY COEFFICIENTS TO DETERMINE SOLVENT EXTRACTION MECHANISM FOR COMPONENTS OF NUCLEAR WASTE

Measurement of Low Levels of Alpha in 99M0Product Solutions

MULTIGROUP BOLTZMANN FOKKER PLANCK ELECTRON-PHOTON TRANSPORT CAPABILITY IN M C N P ~ ~ DISCLAIMER

Optimization of NSLS-II Blade X-ray Beam Position Monitors: from Photoemission type to Diamond Detector. P. Ilinski

Applications of Pulse Shape Analysis to HPGe Gamma-Ray Detectors

~ _- IDOCLRXKT DMSP SATELLITE DETECTIONS OF GAMMA-RAY BURSTS. J. Terrell, NIS-2 P. Lee, NIS-2 R W.

Use of Gamma Rays from the Decay of 13.8-sec "Be to Calibrate a Germanium Gamma Ray Detector for Measurements up to 8 MeV

Ray M. Stringfield Robert J. Kares J. R. Thomas, Jr.

PROJECT PROGRESS REPORT (03/lfi?lfibr-~/15/1998):

Plutonium 239 Equivalency Calculations

The photoneutron yield predictions by PICA and comparison with the measurements

Experiment. The Pinhole Neutron. Pinex. c. c. sartain UCRL-ID November 21,1958

Los Alamos CQFSF, DISTRIBUTION OF THIS DOCUMENT IS WLtrVmED. Preliminary Results of GODIVA-IV Prompt Burst Modeling. R. H.

J. T. Mihalczo. P. 0. Box 2008

Further Investigation of Spectral Temperature Feedbacks. Drew E. Kornreich TSA-7, M S F609

SPHERICAL COMPRESSION OF A MAGNETIC FIELD. C. M. Fowler DISCLAIMER

Analysis of Shane Telescope Aberration and After Collimation

Turbulent Scaling in Fluids. Robert Ecke, MST-10 Ning Li, MST-10 Shi-Yi Li, T-13 Yuanming Liu, MST-10

RUDOLPH J. HENNINGER, XHM PAUL J. MAUDLIN, T-3 ERIC N. HARSTAD, T-3

IMAGING OF HETEROGENEOUS MATERIALS BY. P. Staples, T. H. Prettyman, and J. Lestone

m w n? r i OF,THISDOCUMENT IS UNLIMITED

A Germanium Detector with Optimized Compton Veto for High Sensitivity at Low Energy

Plasma Response Control Using Advanced Feedback Techniques

A Distributed Radiator, Heavy Ion Driven Inertial Confinement Fusion Target with Realistic, Multibeam Illumination Geometry

Los Alamos IMPROVED INTRA-SPECIES COLLISION MODELS FOR PIC SIMULATIONS. Michael E. Jones, XPA Don S. Lemons, XPA & Bethel College Dan Winske, XPA

Development of a High Intensity EBIT for Basic and Applied Science

DISCLAIMER. and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

(4) How do you develop an optimal signal detection technique from the knowledge of

PROJECT PROGRESS REPORT (06/16/1998-9/15/1998):

RESEARCH OPPORTUNITIES AT THE CNS (Y-12 AND PANTEX) NUCLEAR DETECTION AND SENSOR TESTING CENTERS (NDSTC)

sample-specific X-ray speckle contrast variation at absorption edges $ & ~ 0

TOWARDS EVEN AND ODD SQUEEZED NUMBER STATES NIETO, MICHAEL M

The Concentration of 236 Pu Daughters in Plutonium for Application to MOX Production from Plutonium from Dismantled US Nuclear Weapons

ust/ aphysics Division, Argonne National Laboratory, Argonne, Illinois 60439, USA

0STI. E. Hammerberg, XNH MD SIMULATIONS OF DUSTY PLASMA CRYSTAL FORMATION: PRELIMINARY RESULTS M. J. S. Murillo, XPA

Tell uric prof i 1 es across the Darrough Known Geothermal Resource Area, Nevada. Harold Kaufniann. Open-file Report No.

9 7og$y4- International Conference On Neutron Scattering, Toronto August Spin Dynamics of the reentrant spin glass Fe0.7A10.3.

Excitations of the transversely polarized spin density. waves in chromium. E3-r 1s

The Radiological Hazard of Plutonium Isotopes and Specific Plutonium Mixtures

A Two-Dimensional Point-Kernel Model for Dose Calculations in a Glovebox Array. D. E. Kornreich and D. E. Dooley

ASTER CONF-~W OSTI MAY DISTRIBUTION OF THIS

Alamos National Laboratory is operated by the University of California for the United States Department of Energy under contract W-7405-ENG-36

HEAT TRANSFER AND THERMAL STRESS ANALYSES OF A GLASS BEAM DUMP

BWXT Y-12 Y-12. A BWXT/Bechtel Enterprise SMALL, PORTABLE, LIGHTWEIGHT DT NEUTRON GENERATOR FOR USE WITH NMIS

Los Alamos. QSTI Author(s): OCT ENERGY DEPENDENT BIAS IN PLUTONIUM VERIFICATION MEASUREMENTS USING THERMAL

Reactors and Fuels. Allen G. Croff Oak Ridge National Laboratory (ret.) NNSA/DOE Nevada Support Facility 232 Energy Way Las Vegas, NV

UNIT OPERATIONS AND CHEMICAL PROCESSES. Alan M. Krichinsky

ions which are abundant in waste water. Since zeolites are

Laser-Modulator System

Modeling Laser and e-beam Generated Plasma-Plume Experiments Using LASNEX

Fission-Fusion Neutron Source

Alex Dombos Michigan State University Nuclear and Particle Physics

in the pinch. This paper describes the computer modeling behind the shielding design of a

GA A25658 PRECISION X-RAY OPTICAL DEPTH MEASUREMENTS IN ICF SHELLS

GA A26057 DEMONSTRATION OF ITER OPERATIONAL SCENARIOS ON DIII-D

Summary Report: Working Group 5 on Electron Beam-Driven Plasma and Structure Based Acceleration Concepts

EFFECTS OF AXIAL HEAT CONDUCTION AND MATERIAL PROPERTIES ON THE PERFORMANCE CHARACTERISTICS OF A THERMAL TRANSIENT ANEMOMETER PROBE

Lawrence Berkeley National Laboratory Lawrence Berkeley National Laboratory

GA A22722 CENTRAL THOMSON SCATTERING UPGRADE ON DIII D

Meraj Rahimi, JAI Co. Dale Lancaster, TRW Environmental Safety Systems

R. A. Bartsch, Z. Y. Zhang, S. Elshani, and W. Zhao

DE '! N0V ?

Cable Tracking System Proposal. Nick Friedman Experimenta1 Facilities Division. June 25,1993. Advanced Photon Source Argonne National Laboratory

Capabilities for Testing the Electronic Configuration in Pu

INITIAL RESULTS OF THE COMMISSIONING OF THE HRIBF RECOIL MASS SPECTROMETER

Safety analyses of criticality control systems for transportation packages include an assumption

J. C. Batchelder', K. S. Toth2, D. M. Moltz3, E. F. Zganjarl, T. J. Ognibene3, M. W. Rowe3, C. R. Binghan12.~,J. Powell3, and B. E.

Multi-Scale Chemical Process Modeling with Bayesian Nonparametric Regression

Scaling between K+ and proton production in nucleus-nucleus collisions *

Use of AVHRR-Derived Spectral Reflectances to Estimate Surface Albedo across the Southern Great Plains Cloud and Radiation Testbed (CART) Site

ASTER. Dose Rate Visualization of Radioisotope Thermoelectric. Generators. RECElVED BEC OF THIS DOCUMEMT IS UNLlMIi L, Hanford Company

Data Comparisons Y-12 West Tower Data

PLASMA MASS DENSITY, SPECIES MIX AND FLUCTUATION DIAGNOSTICS USING FAST ALFVEN WAVE

ITP Filtrate Benzene Removal Alternatives

: Y/LB-16,056 OAK RIDGE Y-12 PLANT

A lattice dynamical investigation of zircon (ZrSiOJ has been carried out to obtain a

INTERMOLECULAR POTENTIAL FUNCTIONS AND HIGH RESOLUTION MOLECULAR SPECTROSCOPY OF WEAKLY BOUND COMPLEXES. Final Progress Report

BASAL CAMBRIAN BASELINE GEOLOGICAL CHARACTERIZATION COMPLETED

SOME ENDF/B-VI MATERLALS. C. Y. Fu Oak Ridge National Laboratory Oak Ridge, Tennessee USA

ITU-Nuclear Safeguards and Security Unit

Two-Screen Method for Determining Electron Beam Energy and Deflection from Laser Wakefield Acceleration

Parametric Instabilities in Laser/Matter Interaction: From Noise Levels to Relativistic Regimes

OAK RIDGE NATIONAL LABORATORY

Contractor Name and Address: Oxy USA, Inc. (Oxy), Midland, Texas OBJECTIVES

RECEIVED SEQ

PROGRESS REPORT JULY TO SEPTEMBER

N. Tsoupas, E. Rodger, J. Claus, H.W. Foelsche, and P. Wanderer Brookhaven National Laboratory Associated Universities, Inc. Upton, New York 11973

ORNL/TM-2002/118 Plutonium Production Using Natural Uranium From the Front-End of the Nuclear Fuel Cycle

Flipping Bits in the James Webb Space Telescope s Cameras

The temperature dependence of the C1+ propylene rate coefficient and the Arrhenius fit are shown in Figure 1.

The Graphite Isotope Ratio Method (GIRM): A Plutonium Production Verification Tool

LANSCE-1. Preprint LAUR Title: COMPARISON OF BEAM-POSITION-TRANSFER FUNCTIONS USING CIRCULAR BW-POSITION MONITORS

Transcription:

LA-"'- 96-3646 Title: HYBRD KED/XRF MEASUREMENT OF MNOR ACTNDES N REPROCESSNG PLANTS Author(s): Submitted to: S. T. Hsue and M. L. Collins Alternate Nuclear Material Conference Aiken, SC October 15-17, 1996 (FULL PAPER) Los Alamos NATONAL LABORATORY Lw Alarnos National Laboratory, an affirmative actionhqual opportunity empidyer, is operated by the University of California for the U.S. Department of Energy under contract W-7405-ENG-36. By acceptance of this article, the publisher recognizes that the U.S. Government retains a nonexclusive, royalty-free license to publish or reproduce the publishedform of this contribution, or to allow others to do so,for US. Government purposes.the Los AlaNational Laboratory requests that the publisher idmtiiy this article as work performedunder the auspices of the U.S. Department of Energy. OF nm FOanNoU6RS ST2829tOfi)t

This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus. product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or sentice by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors txptessed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

DSCLAMER Portions of this document may be illegible in electronic image products. mages are produced from the best available original document.

, HYBRD KED/XRF MEASUREMENT OF MNOR ACTNDES N REPROCESSNG PLANTS, S.-T. Hsue and M. L. Collins Group NS-5, MS-E540 Los Alamos National Laboratory Los Alamos, NM 87545 USA NTRODUCTON Minor actinides have received considerable attention recently in the nuclear power industry. Because of their potential value as recycle fuels in thermal and breeder reactors, reprocessing plants may have an economic incentive to extract Np, Am, and Cm &om their waste streams. This report discusses the technique of hybrid densitometry and its potential to measure Np and Am in reprocessing plants. Precision estimates are made for the hybrid analysis of Np and Am in two types of dissolver solutions.. HYBRD SYSTEM The hybrid system incorporates two solution assay techniques: k-edge absorption densitometry (KED) and x-ray fluorescence (XRF). A close-up view of the Los Alamos Hybrid Densitometer is shown in Figure 1. The basic components of the hybrid system are an x-ray generator, glass sample vial, and separate high-resolution detectors for KED and XRF. The sample itself may contain any number of actinides dissolved in nitric acid. Figure. Close-up view of Los Alamos Hybrid Densitometer System. The x-ray generator irradiates the sample with a filtered x-ray beam. The KED detector is positioned behind the sample, and measures the transmitted portion of the beam. +e XRF detector is positioned behind a long, narrow collimator that points toward the front of the sample vial. The angle between the incident beam and XRF collimator is 30 degrees. The XRF detector measures fluorescedxrays that are emitted from the front portion of the solution. 1

n hybrid analysis, KED is used to determine the concentration of the major element, usually U or Pu. XRF is used to determine various ratios of concentrations, such as UPu, Pu/Arn, and Pu/Np. Measured ratios are used to determine the ratio of each minor element to the major element. t is then a simple matter to calculate the concentrations of the minor elements. Hybrid analysis takes advantage of the strengths of the KED and XRF techniques. 11. PROCESS FLOW The process flow for a conventional reprocessing plant is illustrated in Figure 2. Spent fuel is placed in the fuel storage facility prior to reprocessing. n the first stage of reprocessing, fuel rods are chopped into small pieces. The resulting mixture is leached in nitric acid to form the dissolver solution. Most fission products and Am are removed in the first extraction cycle. Additional extraction steps are required to separate U and Pu from the remaining elements. Evaporation is performedto concentrate the U and Pu solutions, forming the product solutions. Figure 2. Process jlow schematic for a conventional reprocessing plant. Key measurement points are labeled K1 through K3. AEA and Euratom have been using the hybrid KEDKRF technique to assay the dissolver solution samples, and KED to assay the U and Pu product solutions. The dissolver solution is monitored at key measurement point K1. The U and Pu product solutions are monitored at key measurement points K2 and K3, respectively. By measuring U and/or Pu concentrations at these three measurement points, it is possible to determine the material balance of U and Pu. f a reprocessing plant extracted Am and Np, its process flow might resemble that of Figure 3. n this scenario, Am would be separated from the high-activity effluent of the first extraction cycle. Np would be separated from the effluent of the Pu extraction cycle. Evaporation steps would be performed to concentrate the Am and Np solutions. Such a plant would have four product solutions: U, Pu, Np, and Am. As in the conventional reprocessing plant, the dissolver solution would be monitored at key measurement point K1. A hybrid KEDKRF densitometer would be used to measure the U, Pu, Np, and Am concentrations in the dissolver solution. The Np and Am product solutions are monitored at key measurement points K4 and K5, respectively. By measuring the Np and/or Am concentrations at these three measurement points, it would be possible to determine the material balance of Np and Am. 2

HAW satto E - Figure 3. Process flow for a hypothetical reprocessing plant, showing separation of Np and Am. Key measurement points are labeled K through K.5. 111. DSSOLVER SOLUTONS n this study, two types of dissolver solutions were considered. The first is from a fast breeder reactor (FBR) reprocessing plant; the other from a light water reactor (LWR) reprocessing plant. These solutions are characterized in Table 1. Table 1. Comparison of FBR and LWR Dissolver Solutions. FBR LWR Dissolver Dissolver U Concentration (g/l) 200 200 Pu Concentration (g/l) 50 2 PdNp Ratio 10 30 PdAm Ratio 10 30 We have developed computer codes that simulate the performanceof the hybrid These codes generate KED and XRF spectra that correspond to a given solution. Simulated spectra for the FBR and LWR dissolver solutions are illustrated below. All simulated spectra in this study correspond to a live time of 1000 seconds. Figure 4 shows the KED referencespectrum and simulated KED spectra for FBR and LWR dissolver solutions. The K absorption edge of uranium (at 115.606 kev) is clearly visible in both the FBR and LWR spectra. The K absorption edge of Pu (at 121.797 kev) is prominent in the FBR spectrum, but not in the LWR spectrum. 3

d 1.l.ofmi V 1.W3 -FBR Diiofver (KED) Figure 4. Simulated KED Spectra for FBR and LWR Dissolver Solutions. spectrum is uppermost trace in graph. Reference The differencesbetweenthe FBR and LWR spectra are more readily observed if the spectra are plotted in LnLn( l/transmission) versus Ln(Energy) space. Because of the energy dependence of mass attenuation coefficients,we expect measured data to be linear on either side of each absorption edge in LnLn(l/T) vs. Ln(Energy) space. This can be seen in Figure 5. Single element KED analysis is performed by doing a linear fit in this space, using regions above and below the edge. The concentration of the element is calculated using the results of the linear fitting. n Figure 5, the U and Pu edges are prominent for the FBR dissolver solution. Very small Np and Am edges can also be observed in the FBR data. n the LWR data, a Pu edge can hardly be spotted, and the Np and Am edges are unidentifiable.... e U t R. v...-i N. ~ v..-. ~b h ' e :?= : 1 A ;.. FBRDiiohrsr ::...... i LwRDissdver) FitRegkns i ;----E* Po~ition~ i d....... _ LnfCkannaf) Figure 5. Simulated KED spectra for FBR and LWR dissolver solutions, plotted in LnLn(l/T) vs Ln(EnerD) space. Positions of absorption edges are marked. 4

* Figure 6 shows the XRF referencespectrum and simulated XRF spectra for FBR and LWR dissolver solutions. For each element present in a simulated solution, 10 x-ray peaks are generated. These include the &,, &*, and & peaks, and various Kp peaks. Several of the 40 x-ray peaks simulated in the dissolver solutions can be observed in Figure 6. The K, peaks are seen below 108 kev and the K, peaks are found above 1 10 kev. 80..,.:.... :.... :.... :.... :.... :.... :.... :.... 70 Bo 90 loo t0 $20 130 140 150 Energy WW Figure 6. Simulated XRF spectra for FBR and LWR dissolver solutions. spectrum is lowest trace on graph. Reference The & peaks are of primary interest in XRF analysis. Figure 7 compares the simulated FBR and LWR spectra, shown with the reference spectrum subtracted. The range of energies was narrowed to feature the K, peaks of U, Np, Pu, and Am. Note that the uranium K, peaks ofthe FBR spectrum are slightly smaller than those of the LWR spectrum. This is due to attenuation effects within the FBR dissolver solution, which contains more Pu, Np, and Am. Figure 7. Comparison of XRF Spectra for FBR and LWR Dissolver solutions. spectrum was subtracted f o m both series. Reference

.. The Pu K, peaks in the FBR spectrum have a significantly greater area than those in the LWR spectrum because there is much more Pu to fluoresce in the FBR dissolver solution. Similar observations can be made regarding the K, peaks of Np and Am. n the LWR dissolver solution spectrum, the K, xrays of Np and Am cannot be distinguished from noise. V. ESTMATED PRECSON Hybrid analysis was performed on the simulated FBR and LWR dissolver solution spectra. First, the XRF spectra were analyzed to determine the percent uncertainties in the UPu, Pu/Np, and PdAm ratios. Then the KED spectra were analyzed to determine the percent uncertainty in the concentration of the major element. n KED analysis, the fixed ratio technique was This technique utilizes UPu, Pu/Np, and PdAm ratios to mathematically strip out the attenuation effects of minor elements in the solution. Singleelement KED analysis is performedon the deattenuated spectrum to determine the concentration of the major element in the solution. n this study, the actual ratios known from simulation were used in the fixed-ratiotechnique. Hybrid results for FBR and LWR dissolver solutions are shown below in Table 2. Uranium was the major element in KED analysis for both dissolver solutions. Table 2. Estimated Hybrid Precision for FBR and LWR Dissolver Solutions. FBR Dissolver LWR Dissolver KED o(u) 0.2% 0.2Yo XRF O(UPU) 0.2% 1.4% 0.8% NA XRF o(pu/np) XRF o(pu/am) 0.9% NA 1 With the FBR dissolver solution, the x-ray peaks of Np and Am were readily identified and measured by the XRF analysis code. No sample preparation is needed for the FBR dissolver solution. The situation is different for the LWR dissolver solution. Recall that in Figure 7, the K, peaks of Np and Am in the LWR spectrum were indistinguishable from noise. This was verified by the XRF analysis code, which did not detect the presence of Np or Am in the LWR dissolver solution. We therefore cannot expect to measure Np or Am in the straight LWR dissolver solution using the Hybrid technique. n order for the hybrid system to measure Np and Am at key measurement point K1 in the LWR reprocessing plant, some preparation of the dissolver solution sample would be required. This would involve chemical separation to remove most of the uranium.from the dissolver solution. Evaporation would also be needed to concentrate the remaining liquid severalfold. n this study, three preparation scenarios were considered for the LWR dissolver solution. These are detailed in Table 3 below. Table 3. Possible Preparations of LWR Dissolver Solution. Solution 1 Solution 2 Solution 3 Separation Quality Fair Good Excellent U Removal 97.0% 99.0% 99.9% Evaporation factor Known U (g/l) Known Pu (g/l) 40 40 100 6

. * c * Simulated KED and XRF spectra were generated for the above solutions. Hybrid analysis, as described earlier, was performed on the simulated spectra. The major element in KED analysis was U for solution 1 and Pu for solutions 2 and 3. The results for the prepared LWR solutions are shown in Table 4. Table 4. Estimated Hybrid Precision for Prepared LWR Solutions. Solution 1 Solution 2 Solution 3 0.2% KED o(u) 0.5% 0.2% KED ~ ( P u ) 0.2% 0.3% 0.4% XRF o(u/pu) 2.3% 2.1% 1.O% XRF o(pu/np) 2.4% 2.2% 1.1% XRF o(pu/am) V. CONCLUSONS Hybrid KEDKFW densitometer systems now in operation at reprocessing plants have the potential to measure Np and Am, in addition to U and PU. No hardware alterations would be required in these systems. However, the analysis software would need to be upgraded. New hybrid analysis techniques for measuring Np and Am would be incorporated. At an FBR reprocessing plant, Np and Am could be measured in dissolver solution samples with no sample preparation. The estimated precision for a 1000-s assay is 0.8% for Np and 0.9% for Am. At an LWR reprocessing plant, dissolver solution samples would require some preparation. This preparation would involve partial U separation (97% to 99.9% removal), and evaporation (20 to 50 fold concentration). The estimated precision for a 1000 s assay ranges from 1.0% to 2.3% for Np and from 1.1% to 2.4% for Am. The precision depends upon the extent of sample preparation. REFERENCES 1. 2. 3. 4. J. E. Stewart, R. B. Walton, et. al., Measurement and Accounting of the Minor Actinides Produced in Nuclear Power Reactors. Los Alamos National Laboratory report LA-13054-MS, pp. 2-3 (January 1996). M. L. Collins and S.-T. Hsue, Simulation of X-Ray Fluorescence Spectra, Los Alamos National Laboratory report LA-UR-96-2603 (to be published in 37th Annual Nuclear Materials Management, Proceeding ssue). S.-T. Hsue and M. L. Collins, Simulation of Absorption Edge Densitometry. Los Alamos National Laboratory report LA-12874-MS (November 1994). S.-T. Hsue and M. L. Collins, New Analysis Technique for K-Edge Densitometry Spectra. Los Alamos National Laboratory report LA-UR-95-3222. Proceedings of the Fifth nternational Conferenceon Facility Operations-Safeguards nterface, American Nuclear Society, Jackson Hole, Wyoming, September 1995. 7