ENRICHMENT AND URANIUM MASS FROM NMIS FOR HEU METAL



Similar documents
Overview of Nuclear Detection Needs for Homeland Security. Abstract

ALGORITHM TO DETERMINE THE CALIBRATION PARAMETERS FOR A NDA METHOD OF INVENTORY VERIFICATION IN A DIFFUSION ENRICHMENT CASCADE

An Innovative Method for Dead Time Correction in Nuclear Spectroscopy

Experiment 10. Radioactive Decay of 220 Rn and 232 Th Physics 2150 Experiment No. 10 University of Colorado

WM2012 Conference, February 26 March 1, 2012, Phoenix, Arizona, USA

A Comparison of an HPGe-based and NaI-based Radionuclide Identifier (RID) for Radioactive Materials

MONTE CARLO SIMULATION OF THE FULL MULTIPLICITY DISTRIBUTIONS MEASURED WITH A PASSIVE COUNTER

Antoine Henri Becquerel was born in Paris on December 15, 1852

A Digital Spectrometer Approach to Obtaining Multiple Time-Resolved Gamma-Ray. Spectra for Pulsed Spectroscopy. W. K. Warburton a

Tutorial 4.6 Gamma Spectrum Analysis

Michael I. Frank and James K. Wolford, Jr. Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, CA ABSTRACT

INSPECTION REPORT. Alleged Nuclear Material Control and Accountability Weaknesses at the Department of Energy's Portsmouth Project

Copyright 2007 Casa Software Ltd. ToF Mass Calibration

Cosmic Ray Muon Scattering Tomography for Security Applications

ATTACHMENT 8: Quality Assurance Hydrogeologic Characterization of the Eastern Turlock Subbasin

INFO-0545 RADIOISOTOPE SAFETY MONITORING FOR RADIOACTIVE CONTAMINATION

AN INVESTIGATION INTO THE USEFULNESS OF THE ISOCS MATHEMATICAL EFFICIENCY CALIBRATION FOR LARGE RECTANGULAR 3 x5 x16 NAI DETECTORS

Variance Reduction Techniques for the Monte Carlo Simulation of Neutron Noise Measurements

Neutron Detection Setups proposed for

A Tool for Criticality Accident Emergency Planning, Training and Response

TAGUCHI APPROACH TO DESIGN OPTIMIZATION FOR QUALITY AND COST: AN OVERVIEW. Resit Unal. Edwin B. Dean

Use of electronic seals and remote data transmission to increase the efficiency of safeguards applied in a static Plutonium store

PROSPECT: Precision Reactor Oscillation and Spectrum experiment

V K Raina. Reactor Group, BARC

Chapter 7. Sealed-bid Auctions

Electrical tests on PCB insulation materials and investigation of influence of solder fillets geometry on partial discharge

A Review of Emerging Gamma Detector Technologies for Airborne. Radiation Monitoring

Forecasting in supply chains

Nuclear Physics Lab I: Geiger-Müller Counter and Nuclear Counting Statistics

CRIIRAD report N Analyses of atmospheric radon 222 / canisters exposed by Greenpeace in Niger (Arlit/Akokan sector)

Self-adjusting Importances for the Acceleration of MCBEND

Concepts in Investments Risks and Returns (Relevant to PBE Paper II Management Accounting and Finance)

Chapter 11 Cash Flow Estimation and Risk Analysis ANSWERS TO SELECTED END-OF-CHAPTER QUESTIONS

How To Understand The Sensitivity Of A Nuclear Fuel Cask

NUCLEAR BOREHOLE LOGGING TECHNIQUES DEVELOPED BY CSIRO-EXPLORATION AND MINING FOR IN SITU EVALUATION OF COAL AND MINERAL DEPOSITS

Sound Power Measurement

How to report the percentage of explained common variance in exploratory factor analysis

Online Appendices to the Corporate Propensity to Save

Radioanalytical Data Validation Issues and Solutions

Monte Carlo Path Tracing

THE STATISTICAL TREATMENT OF EXPERIMENTAL DATA 1

Aspen Utilities. Energy Management and Optimization System for energy intensive industry sectors. The Challenge: Reduction of Production Costs

Evaluating Laboratory Data. Tom Frick Environmental Assessment Section Bureau of Laboratories

Using simulation to calculate the NPV of a project

W. C. Reinig. Savannah River Laboratory E. I. du Pent de Nemours and Company Aiken, South Carolina 298o1

Open Source Software zur Vertrauensbildung in der Abrüstungsverifikation: Simulation von Neutronenmultiplizitätsmessungen mit Geant4

Forensic Science Standards and Benchmarks

A joint control framework for supply chain planning

Environmental Radiation Monitoring in Taiwan

Marketing Mix Modelling and Big Data P. M Cain

centre for radiation protection

Results of Airborne Monitoring by the Ministry of Education, Culture, Sports, Science and Technology and the U.S. Department of Energy

April 30, 2013 E M. Environmental Management. safety performance cleanup closure

Customer: Cardiff Hospital NHS (United Kingdom) Machine:

Innovative Technology Verification Report

Dedicated computer software to radiation dose optimization for the staff performing nuclear medicine procedures

Management and Interpretation of Real-time Data Collected by US EPA s Environmental Air Radiation Monitoring Network (RadNet)

Questionnaire for NORM service providers

SPECIFICATIONS, LOADS, AND METHODS OF DESIGN

ASSURING THE QUALITY OF TEST RESULTS

Categorisation of Active Material from PPCS Model Power Plants

WM2012 Conference, February 26 -March 1, 2012, Phoenix, Arizona, USA

INTEGRATED OPTIMIZATION OF SAFETY STOCK

Nuclear Criticality Safety Division TRAINING MODULE CSG-TM-016 COG SOFTWARE

Treatment Centers for Radioactive Waste

Basic Concepts of X-ray X Fluorescence by Miguel Santiago, Scientific Instrumentation Specialist

The Monte Carlo method is a statistical STAN ULAM, JOHN VON NEUMANN, and the MONTE CARLO METHOD. by Roger Eckhardt

A Log-Robust Optimization Approach to Portfolio Management

Measurements for nuclear forensic characterisation: synergies between international security applications

Calorimetry in particle physics experiments

MATERIALS LICENSE. 1. American Centrifuge Operating, LLC 3. License Number: SNM-2011, Amendment 4

A New Quantitative Behavioral Model for Financial Prediction

BECHTEL JACOBS COMPANY ORR WASTE CERTIFICATION PROGRAM DOCUMENT CONTROL SYSTEM

USE OF REFERENCE MATERIALS IN THE LABORATORY

IMPLEMENTATION OF A MANAGEMENT SYSTEM FOR OPERATING ORGANIZATIONS OF RESEARCH REACTORS

Assessment of environmental radiation monitoring data in Hungary following the Fukushima accident

EVALUATING SOLAR ENERGY PLANTS TO SUPPORT INVESTMENT DECISIONS

Monte Carlo simulation of a scanning whole body counter and the effect of BOMAB phantom size on the calibration.

Nuclear Security Glossary

Chapter 18: The Structure of the Atom

National Radiation Air Monitoring Network National Environmental Monitoring Conference San Antonio -- August 6, 2013

SHORT-TERM STABILITY TEST FOR URANIUM SOIL CANDIDATE A REFERENCE MATERIAL

THE STATUS OF NUCLEAR INSPECTIONS IN IRAQ: AN UPDATE. Meeting of the United Nations Security Council. New York 7 March 2003

Master Degree in Nuclear Engineering: Academic year

Creating Synthetic Temporal Document Collections for Web Archive Benchmarking

WM2012 Conference, February 26-March 1, 2012, Phoenix, Arizona, USA

HIGHLY ENRICHED URANIUM INVENTORY

Data Preparation and Statistical Displays

QUANTITATIVE IMAGING IN MULTICENTER CLINICAL TRIALS: PET

Checking of quality on production

Transcription:

ABSTRACT ENRICHMENT AND URANIUM MASS FROM NMIS FOR HEU METAL J. K. Mattingly, T. E. Valentine, J. T. Mihalczo, L. G. Chiang, R. B. Perez Oa Ridge National Laboratory Oa Ridge, Tennessee 37831-6004 Recently, the Nuclear Materials Identification System (NMIS) was employed to verify both the mass and enrichment of a number of high-enriched uranium (HEU) metal items stored at the Oa Ridge Y-12 Plant. NMIS was applied for this measurement as an active neutron interrogation system; the measurement performed was similar in nature to a pulsed neutron measurement in that the distribution of detector counts following source emission was accumulated and subjected to analysis. In order to develop a calibration surface versus mass and enrichment, Monte Carlo models of the item geometry were employed to calculate the distribution for a matrix of independently varying masses and enrichments spanning the nominal declared mass and enrichment of the actual items. Each calculated distribution was then decomposed into its moments, and an empirical model of each moment as a function of mass and enrichment was developed. These models were then simultaneously analytically inverted to yield a nonlinear calibration surface that predicted mass and enrichment given the low-order moments of a measured distribution. The uncertainty in the calibration was estimated using standard squared-error minimization and propagation-of-error techniques, and the bias (and its uncertainty) in the calibration was evaluated using measurements of several randomly selected samples. No single mass or enrichment verified using this method deviated from declaration by more than 5.0%. The typical, i.e., root-mean-squared, error in mass was only 1.6% of the declaration, and the typical error in enrichment was only 1.5% of the declaration. As a result, a finding previously issued for this storage area by the Department of Energy, Oa Ridge Operations, (DOE-ORO) was resolved. INTRODUCTION In 1999, DOE-ORO issued a finding for a particular storage area at the Oa Ridge Y-12 Plant; to be resolved, this finding required that the mass and enrichment of a number of HEU metal items stored in the area be verified. However, the Oa Ridge Y-12 Plant Nuclear Materials Control and Accountability (NMC&A) Organization determined that it could not, by standard techniques, safely verify the mass and enrichment of HEU metal items in this particular storage area due to the significant potential for the spread of airborne contamination. Ordinarily, the mass of these items would have been measured using a scale, and their enrichment would have been estimated using passive gamma spectrometry. However, the former required the items to be removed from their storage containers, and the latter was similarly difficult to implement unless the items were removed from their storage containers. Unfortunately, no hood that could be transported to the storage area was available, and radiological control dictated that a fixed hood outside the area could not be used extensively without rising the spread of airborne contamination to the rest of the facility. In any event, the only suitable fixed hood in the same facility was at that time dedicated to higher priority tass. Consequently, the Oa Ridge National Laboratory was ased if it would be possible to use the Nuclear Materials Identification System (NMIS) to verify the mass and enrichment of these items in-situ, i.e., without removing them from their containers and without removing the containers from the storage area. Chiang, et al., describes the operational aspects of these verification measurements. 1

Prior to this, NMIS had never been used to estimate the enrichment of uranium metal. After performing a series of measurements on ten samples selected at random from the storage area, the subsequently described method to simultaneously estimate both the mass and enrichment of these HEU metal items was developed. METHOD NMIS was operated as an active neutron interrogation system for this application. A small (~ 1 2g) 252 Cf ionization chamber was employed as the active source and an array of fast plastic scintillators was used to detect neutrons and gammas emitted by the inspected items in response to the source. NMIS acquires a variety of statistics, but early in this application it was determined that only the distribution of detector counts following 252 Cf fission would be subjected to analysis in order to estimate the mass and enrichment of the inspected items. In this respect, the measurement was similar in nature to a pulsed neutron measurement. The items to be inspected exhibited only small deviations from nominal in the declared mass and enrichment. So, in order to develop a calibration surface versus mass and enrichment, MCNP-DSP models of the item geometry were employed to calculate the distribution for a matrix of independently varying masses and enrichments. 2 The masses and enrichments modeled were selected to span the nominal declared mass and enrichment of the actual items. Each calculated distribution R (9 ) of detector counts following 252 Cf fission, where 9 denotes the timedelay between 252 Cf fission and detection events, was then decomposed into moments of the form n M 9 R( 9 ). n In particular, note that the zeroth moment M 0 is simply the source-correlated detector count rate (i.e., the area under the distribution) and the first moment M 1 is the product of the source-correlated count rate with the distribution-weighted mean delay 9 : 9 R( 9 ) M1 M 0 b9 M 0 b. R( 9 ) Higher order moments similarly yield the product of the source-correlated count rate with the meansquared delay, mean-cubed delay, etc. a Figure 1 illustrates the decomposition of the distribution into moments over the matrix of independently varying masses and enrichments; this decomposition results in a surface that yields a particular moment at a given (mass, enrichment) pair. Empirical models predicting these moments given the mass and enrichment were developed and the model parameters (and their uncertainty) were estimated using standard squared-error minimization techniques. To develop these models, the dependence of each moment as a function of only mass for a fixed enrichment was determined. This dependence was found to have the same trend for all moments and for all enrichments; only the parameters of each trend varied with enrichment. The dependence on only enrichment of these parameters was subsequently determined a Recall that a distribution can be reconstructed from its moments exactly if all the moments are nown (A. Papoulis, Probability, Random Variables, and Stochastic Processes, 2 nd Ed., McGraw-Hill, 1984). In other words, the moments are just an alternate representation of the distribution. Hence, using a few low-order moments to represent the distribution is essentially a rudimentary compression technique.

to produce a family of models that predict a given moment as a simultaneous function of mass and enrichment. Z Y X MOMENT Z 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 MASS ENRICHMENT Figure 1. Illustration of a surface representing a decomposition moment over a matrix of independently varying masses and enrichments These models were then simultaneously analytically inverted to obtain a nonlinear calibration surface of the form mass f ( M 0, M 1), enrichment g( M 0, M1) that predicted mass and enrichment given the two lowest order moments ( M 0 and M 1) of a measured distribution. The uncertainty in the calibration was estimated from that of the model parameters using standard propagation-of-error methods. The Monte-Carlo-calculated calibration was not without error, i.e., it yielded a bias in the estimated mass and enrichment when applied to a measured distribution. This bias, and its uncertainty, was evaluated by measuring ten samples randomly selected from the inventory of items to be inspected. These ten items were set aside for independent verification using a scale and gamma spectrometry. It must be noted that only these ten items were independently verified. The preceding model, once corrected for the bias in the Monte Carlo calculations, was then applied to verify the mass and enrichment of all other inspected items.

RESULTS No single verification using the preceding method yielded an estimated mass or enrichment that deviated from the declared by more than 5.0% (see Fig. 2 for typical results and Table 1 for a summary of the results). The root-mean-squared (RMS) deviation of the estimated mass relative to the declared mass was only 1.6%, and the RMS deviation of the estimated enrichment relative to the declared enrichment was only 1.5%. The (arithmetic) mean deviation of the estimated mass relative to the declared was +0.2%, and the mean deviation of the estimated enrichment relative to the declared was 0.2%. The RMS relative uncertainty of the mass estimate was 5.3% of the estimate, and the RMS relative uncertainty in the enrichment estimate was 9.6% of the estimate. Figure 2. Typical relative deviations in the verification of mass and enrichment

Table 1. Summary of relative uncertainty and deviations in the verification of mass and enrichment Mass Enrichment RMS Relative Uncertainty 5.3% 9.6% Relative Deviation Minimum -4.0% -4.6% Maximum 5.0% 3.7% RMS 1.6% 1.5% Mean 0.2% -0.2% It is important to note that this method, as it currently exists, is probably not generally applicable to all uranium metal items. The parameters of the calibration surface are unliely to be strictly independent of geometry and are certainly applicable only over a limited range of masses and enrichments. However, it is liely that with further development, which would necessarily include reconfiguration of the source and detectors to minimize time-of-flight and other geometry-related effects, this method could be extended to a wide variety of uranium metal items. CONCLUSIONS These NMIS measurements were completed expeditiously; each verification too only 6 minutes including the time required to change the sample. Furthermore, no inspected item was removed from its container and no inspected container was removed from the storage area. No spread of airborne contamination was detectable. Following the completion of the verifications and the submission of the results, NMC&A and DOE-ORO accepted the declared mass and enrichment of each item and thereby resolved the finding. The items were subsequently sealed and now only periodic inspection of randomly selected samples is required. REFERENCES 1. L. G. Chiang, J. K. Mattingly, J. A. Ramsey, and J. T. Mihalczo, Verification of Uranium Mass and Enrichment of Highly Enriched Uranium (HEU) Using the Nuclear Materials Identification System (NMIS), Proceedings of the Institute of Nuclear Materials Management 41 st Annual Meeting, July 2000. 2. T. E. Valentine and J. T. Mihalczo, MCNP-DSP: A Neutron and Gamma Ray Monte Carlo Calculation of Source Drive Noise-Measured Parameters, Ann. Nucl. Energy 24, 1271, 1996.