Survey
* Your assessment is very important for improving the workof artificial intelligence, which forms the content of this project
* Your assessment is very important for improving the workof artificial intelligence, which forms the content of this project
NENS Nuclear Energy Environment and Nuclear Security Laboratory Including Below Detection Limit Samples in Decommissioning Soil Sample Analyses Speaker: Jung Hwan Kim KRS presentation (May 27. 2016) & Quantum NQe Nuclear Engineering Department 1 NENS Nuclear Energy Environment and Nuclear Security Laboratory Contents Introduction Purpose of the research Case study Results Conclusions Future work References & Quantum NQe Nuclear Engineering Department 2 NENS Nuclear Energy Environment and Nuclear Security Laboratory Introduction & Quantum NQe Nuclear Engineering Department 3 NENS Nuclear Energy Environment and Nuclear Security Laboratory Introduction Decommissioning is an emerging international issue in the nuclear industry. Termination of an NPP license, involves releasing the facility from regulatory control for either restricted or unrestricted use in the future. Current Domestic Research Focuses on; Development of Clearance Standards Evaluation of Exposure. & Quantum NQe Nuclear Engineering Department 4 NENS Nuclear Energy Environment and Nuclear Security Laboratory Introduction NPP site soil analysis for license termination There are technical problems for finalizing regulations and standards. Hot Spots Observations reported as below the detection limits Observations reported as below the detection limits are caused by: Inherent limitations of measurement methods (e.g. detectors) & Quantum NQe Nuclear Engineering Department 5 NENS Nuclear Energy Environment and Nuclear Security Laboratory Introduction Conventional methods for analyzing soil sampling data: Only use values above detection limit (This ignores non-detects) Replace non-detects with zero Replace non-detects with half of the detection limit (DL) Replace non-detects with DL However, these strategies have limitations: Statistically biased estimate Probabilistic Exposure Assessment is unreliable Predicts a higher dose --- causing higher waste volumes and associated costs & Quantum NQe Nuclear Engineering Department 6 NENS Nuclear Energy Environment and Nuclear Security Laboratory Introduction • To resolve these issues Statistical Techniques were used to analyze a case study 1. Proposed methods for estimating summary statistics (Mean, STD DEV, PCT) • Kaplan-Meier • Regression on Order Statistics (ROS) • Maximum Likelihood Estimation (MLE) 2. Proposed method for estimating confidence intervals • Bootstrapping • These techniques are used by many researchers in the Environmental Science and Technology area. & Quantum NQe Nuclear Engineering Department 7 NENS Nuclear Energy Environment and Nuclear Security Laboratory Introduction – Kaplan-Meier • The Kaplan-Meier method is a nonparametric technique which is the most commonly used for calculating the probability distribution to estimate summary statistics with censored data. • Kaplan-Meier is nonparametric, so it does not assume the data follow a known distribution. • Kaplan-Meier is well-suited for many environmental data sets because it is nonparametric. & Quantum NQe Nuclear Engineering Department 8 NENS Nuclear Energy Environment and Nuclear Security Laboratory Introduction – Kaplan-Meier • Consider the following data set: 20, 20, 10, 1, <0.5, <0.5, <25, <2, <2, 1, 100, 30, 3, <3, 2, 1, 3, 5, <10, <0.5 • Order this data set in decreasing order (Efron’s bias correction): 100, 30, <25, 20, 20, 10, <10, 5, 3, 3, <3, 2, <2, <2, 1, 1, 1, <0.5, <0.5, 0.5 The probability of each data point is as below: The probability of getting a data point less than 100 is 19/20=0.95 The probability of getting a data point below 30 is 18/19=0.947 The location of 30 on the PDF is calculated by 0.95*0.947=0.90 The probability of getting a data point below 20 is 15/17=0.882 The location of 20 on the PDF is calculated by 0.90*0.882=0.794 & Quantum NQe Nuclear Engineering Department 9 NENS Nuclear Energy Environment and Nuclear Security Laboratory Introduction – Kaplan-Meier Value Probability 100 0.95 30 0.90 20 0.794 10 0.741 5 0.684 3 0.570 2 0.507 1 0.253 0.5 0 Table 1. Kaplan-Meier example data & Quantum NQe Nuclear Engineering Department Fig. 1. Kaplan-Meier method example data plot 10 NENS Nuclear Energy Environment and Nuclear Security Laboratory Introduction – ROS • Robust regression on order statistics (ROS) is a semi-parametric method that can be used to estimate summary statistics with censored data. ROS plots the detected values on a probability plot and calculates a linear regression line in order to estimate the parameters. • ROS internally assumes that the underlying population is normal or lognormal. However, the assumption is applied to only the censored data set and not to the full data set. • It is necessary to fit a known distributional model to the detected values on a probability plot. & Quantum NQe Nuclear Engineering Department 11 NENS Nuclear Energy Environment and Nuclear Security Laboratory Introduction – ROS Input Concentration Probability Estimated Concentration 3.2 0.972 3.2 2.8 0.944 2.8 <2 0.815 1.418 <2 0.713 1.143 <2 0.611 0.954 <2 0.509 0.807 <2 0.407 0.683 <2 0.306 0.572 <2 0.204 0.465 <2 0.102 0.349 1.7 0.873 1.7 1.5 0.829 1.5 Table 2. ROS final data & Quantum NQe Nuclear Engineering Department 12 NENS Nuclear Energy Environment and Nuclear Security Laboratory Introduction – MLE • Maximum likelihood estimation (MLE) is a parametric, model-based method that can be used to estimate summary statistics with censored data. Probability plots and other goodness-of-fit techniques should be used to find matching distributions. • Nondetects are distributed in a manner similar to the detected values. • If the assumed model is incorrect, MLE may lead to misleading results. & Quantum NQe Nuclear Engineering Department 13 NENS Nuclear Energy Environment and Nuclear Security Laboratory Introduction – Bootstrap • After generating 100 bootstrap samples, it is possible to find the confidence interval for the mean, calculating the difference between the mean of the original sample and the mean of bootstrap samples. Original sample Bootstrap1 Bootstrap100 Fig. 2. Schematic matrix of original smaple and bootstrap samples & Quantum NQe Nuclear Engineering Department 14 NENS Nuclear Energy Environment and Nuclear Security Laboratory Purpose of the research “Develop a statistical approach that more accurately estimates the required site decontamination necessary to meet current cleanup criteria and validate that compliance.” The expected advantages are: Better Probabilistic Exposure Assessment More Cost Effective & Quantum NQe Nuclear Engineering Department 15 NENS Nuclear Energy Environment and Nuclear Security Laboratory Case study & Quantum NQe Nuclear Engineering Department 16 NENS Nuclear Energy Environment and Nuclear Security Laboratory Case study • There is a monazite powder manufacturing plant. • Some of the plant facilities and soil were contaminated during the manufacturing process. • Facility soil was decontaminated and soil survey conducted. & Quantum NQe Nuclear Engineering Department 17 NENS Nuclear Energy Environment and Nuclear Security Laboratory Case study • The survey consisted of Grid box No.1 and Grid box No.2, each having 30 data points measuring the concentration of U-238 and K-40, in the same area. • In Grid box No.1, 8 data points are below the detection limit for U-238, and 17 for K-40. Grid box No.1 U-238 K-40 (8/30) (17/30) Fig. 3. Schematic diagram of Grid box No.1 & Quantum NQe Nuclear Engineering Department 18 NENS Nuclear Energy Environment and Nuclear Security Laboratory Case study • In Grid box No.2, 10 data points are below the detection limit for U-238, and 9 for K-40. Grid box No.2 U-238 K-40 (10/30) (9/30) Fig. 4. Schematic diagram of Grid box No.2 & Quantum NQe Nuclear Engineering Department 19 NENS Nuclear Energy Environment and Nuclear Security Laboratory Results & Quantum NQe Nuclear Engineering Department 20 NENS Nuclear Energy Environment and Nuclear Security Laboratory U-238 in Grid box No.1 Mean (Bq/g) STD DEV (Bq/g) Pct25 (Bq/g) Median (Bq/g) Pct75 (Bq/g) Ignoring 0.339 0.212 0.123 0.351 0.534 Zero 0.249 0.236 0.012 0.148 0.460 1/2 DL 0.261 0.223 0.048 0.148 0.460 DL 0.274 0.211 0.095 0.148 0.460 MLE(ln) 0.263 0.221 0.065 0.148 0.486 ROS(ln) 0.267 0.218 0.085 0.148 0.460 K-M 0.263 0.221 0.051 0.148 0.486 Table 3. Summary statistics using several estimation methods – U-238 in Grid box No.1 & Quantum NQe Nuclear Engineering Department 21 NENS Nuclear Energy Environment and Nuclear Security Laboratory K-40 in Grid box No.1 Mean (Bq/g) STD DEV (Bq/g) Pct25 (Bq/g) Median (Bq/g) Pct75 (Bq/g) Ignoring 0.092 0.042 0.072 0.094 0.110 Zero 0.040 0.054 0 0 0.087 1/2 DL 0.043 0.051 0.006 0.006 0.087 DL 0.046 0.049 0.012 0.012 0.087 MLE(ln) 0.043 0.051 0.003 0.012 0.091 ROS(ln) 0.046 0.049 0.012 0.012 0.087 K-M 0.054 0.044 0.091 Table 4. Summary statistics using several estimation methods – K-40 in Grid box No.1 & Quantum NQe Nuclear Engineering Department 22 NENS Nuclear Energy Environment and Nuclear Security Laboratory U-238 in Grid box No.2 Mean (Bq/g) STD DEV (Bq/g) Pct25 (Bq/g) Median (Bq/g) Pct75 (Bq/g) Ignoring 0.492 0.274 0.228 0.408 0.7735 Zero 0.328 0.324 0 0.242 0.561 1/2 DL 0.346 0.305 0.055 0.242 0.561 DL 0.364 0.288 0.109 0.242 0.561 MLE(ln) 0.353 0.299 0.102 0.242 0.604 ROS(ln) 0.358 0.294 0.109 0.242 0.561 K-M 0.379 0.277 0.213 0.583 Table 5. Summary statistics using several estimation methods – U-238 in Grid box No.2 & Quantum NQe Nuclear Engineering Department 23 NENS Nuclear Energy Environment and Nuclear Security Laboratory K-40 in Grid box No.2 Mean (Bq/g) STD DEV (Bq/g) Pct25 (Bq/g) Median (Bq/g) Pct75 (Bq/g) Ignoring 0.092 0.067 0.023 0.108 0.135 Zero 0.064 0.070 0 0.026 0.124 1/2 DL 0.066 0.069 0.006 0.026 0.124 DL 0.068 0.067 0.013 0.026 0.124 MLE(ln) 0.067 0.068 0.011 0.026 0.128 ROS(ln) 0.067 0.068 0.012 0.026 0.124 K-M 0.068 0.067 0.026 0.127 Table 6. Summary statistics using several estimation methods – K-40 in Grid box No.2 & Quantum NQe Nuclear Engineering Department 24 NENS Nuclear Energy Environment and Nuclear Security Laboratory Confidence interval using MLE/Bootstrap Cases 90% confidence interval for the mean (Bq/g) 95% confidence interval for the mean (Bq/g) [0.189, 0.413] [0.177, 0.450] [0.025, 0.176] [0.022,0.233] [0.256, 0.554] [0.240, 0.604] [0.043, 0.142] [0.039, 0.165] U-238 in Grid box No.1 (Mean : 0.263) K-40 in Grid box No.1 (Mean : 0.043) U-238 in Grid box No.2 (Mean : 0.353) K-40 in Grid box No.2 (Mean : 0.067) Table 7. Various confidence intervals for the mean using MLE/Bootstrap & Quantum NQe Nuclear Engineering Department 25 NENS Nuclear Energy Environment and Nuclear Security Laboratory Background - RESRAD • RESRAD is a computer model designed to estimate radiation doses and risks from RESidual RADioactive materials. • RESRAD code is used for determining regulatory compliance. • Both the U.S Department of Energy and the U.S. Nuclear Regulatory Commission use 25 mrem/yr as the general limit or constraint for soil cleanup or site decontamination. • RESRAD code has the basic models and parameters, but it can be modified to meet specific need. & Quantum NQe Nuclear Engineering Department 26 NENS Nuclear Energy Environment and Nuclear Security Laboratory Background - RESRAD • RESRAD code can be used to : • Compute potential annual doses or lifetime risks to workers or members of the public resulting from exposures to residual radioactive material in soil • Support an ALARA analysis or a cost benefit analyses that can help in the cleanup decision-making process. Fig. 5. Exposure pathways considered in RESRAD & Quantum NQe Nuclear Engineering Department 27 NENS Nuclear Energy Environment and Nuclear Security Laboratory Background - RESRAD • Assumptions • • • • • • Farmer scenario (Consider all pathways) Municipal landfill Climate data in Daejeon National nutrition survey Default value Did not consider radon and C-14 & Quantum NQe Nuclear Engineering Department 28 NENS Nuclear Energy Environment and Nuclear Security Laboratory Results Cases Maximum Total Dose (t) (mrem/yr) Maximum Excess Cancer Risk (t) Ignoring 29.11 (t=128.3yr) 1.127E-3 (t=100yr) Zero 13.09 (t=128.4yr) 4.985E-4 (t=100yr) 1/2 DL 14.15 (t=128.4yr) 5.396E-4 (t=100yr) DL 15.99 (t=128.3yr) 6.114E-4 (t=100yr) MLE 14.13 (t=128.4yr) 5.388E-4 (t=100yr) Table 8 Maximum Total Dose (t) and Maximum Excess Cancer Risk (t) for the several estimation methods in Grid box No.1 & Quantum NQe Nuclear Engineering Department 29 NENS Nuclear Energy Environment and Nuclear Security Laboratory Conclusions • Summary statistics and confidence intervals were compared to conventional methods. • Proposed methods (MLE, ROS, K-M) were performed using the soil samples from the monazite powder manufacturing plant. • The preliminary evaluation shows that the proposed method can be effectively used to provide • Best Estimate Radioactivity levels at decommissioned NPP site. • Estimates of uncertainty in the Mean Values • RESRAD is used to estimate radiation doses and risks in each case. • Cover thickness is calculated to show the difference between the each method. & Quantum NQe Nuclear Engineering Department 30 NENS Nuclear Energy Environment and Nuclear Security Laboratory Future work • Get the soil data from real decommissioned NPP and conduct all of the above analyses (Yankee Rowe Finished/software & codes). • Economic analysis of the degree of savings using new methodology. • Develop RESRAD input code that allows the inclusion of non-detects. & Quantum NQe Nuclear Engineering Department 31 NENS Nuclear Energy Environment and Nuclear Security Laboratory References [1] Dennis R. Helsel (2005), Nondetects And Data Analysis: Statistics for censored environmental data, John Wiley & Sons, Inc., Hoboken, New Jersey. [2] Zhao, Y., and H.C. Frey, “Quantification of Uncertainty and Variability for Air Toxic Emission Factor Data Sets Containing Non-Detects,” Annual Meeting of the Air & Waste Management Association, Pittsburgh, PA, June 2003 [3] OECD NEA, Cost Estimation for decommissioning: An International Overview of Cost Elements, Estimation Practices and Reporting Requirements, p. 7, 2010 [4] Orbitech, Development of Radioactivity Inference Method and Acceptance Criteria Based on Statistical Approach for Treatment or Disposal of NORM Waste, Feb 2016 [5] Brookhaven National Laboratory, Assessment of Radionuclide Release from Contaminated Concrete at the Yankee Nuclear Power Station, March 2004 [6] Argonne National Laboratory, Examination of Technetium-99 Dose Assessment Modeling with RESRAD (onsite) and RESRAD-OFFSITE, June 2011 [7] EPA, Data Quality Assessment: Statistical Methods for Practitioners, Feb 2006 [8] KHNP, Decontamination Experiment of Contaminated Soil and its Safety Assessment by Residual Radioactivity, 2004 [9] KINS, Establishment of Management Plan for the Disposal of NORM Wastes and Unsuitable Processed Products, Feb 2015 & Quantum NQe Nuclear Engineering Department 32 NENS Nuclear Energy Environment and Nuclear Security Laboratory Thank you & Quantum NQe Nuclear Engineering Department 33 NENS Nuclear Energy Environment and Nuclear Security Laboratory Appendix & Quantum NQe Nuclear Engineering Department 34 NENS Nuclear Energy Environment and Nuclear Security Laboratory Background Instruments & Analysis Program • ORTEC HPGe (GEM-60195-P, 60% efficiency) is utilized. • Counting time is 1,800 sec for all the samples. • ORTEC GammaVision 6.01 is used to analyze. & Quantum NQe Nuclear Engineering Department 35 NENS Nuclear Energy Environment and Nuclear Security Laboratory Appendix Amount of available data Percent Censored < 50 observations > 50 observations < 50% nondetects Kaplan-Meier Kaplan-Meier 50 – 80% nondetects MLE or ROS MLE > 80% nondetects Report only % above a meaningful threshold May report high sample percentiles (90th, 95th) Table 8. Recommended methods for estimation of summary statistics & Quantum NQe Nuclear Engineering Department 36 NENS Nuclear Energy Environment and Nuclear Security Laboratory Appendix – Kaplan-Meier • The nonparametric Kaplan-Meier (K-M) method has always been considered as a standard method for estimating summary statistics of censored survival data. • Left-censored data must be flipped prior to using the K-M method, the procedures of calculating survival probability are computed in a way that is similar to analyses for right censored data, and the results are re-transformed when calculating estimates(mean, median, and other percentiles). • In this case, the highest observed value would have the lowest rank 1. Let S be the survival probability. The survival probability is a product of incremental probabilities that are the probabilities of "surviving" to the next lowest detected limit, given the number of data at and below that detection limit. • The mean of K-M estimator is evaluated as the area under the K-M survival curve for the flipped data after re-transformation. & Quantum NQe Nuclear Engineering Department 37 NENS Nuclear Energy Environment and Nuclear Security Laboratory Appendix – ROS • ROS calculates summary statistics with a regression equation on a probability plot, and is called "regression on order statistics". We used a robust approach to ROS. • Unobserved values are estimated from a regression equation obtained by using observed data. The regression equation is obtained by fitting observed values to the probability plot, and the explanatory variable in the regression is the normal scores of observed values. & Quantum NQe Nuclear Engineering Department 38 NENS Nuclear Energy Environment and Nuclear Security Laboratory Appendix – MLE • The parametric Maximum Likelihood Estimator (MLE) assumes a distribution that will closely fit the observed data. & Quantum NQe Nuclear Engineering Department 39 NENS Nuclear Energy Environment and Nuclear Security Laboratory Appendix – MDA Calculation • 𝑀𝐷𝐶𝑅 = 𝑘2 𝑇𝑠 + 2𝑘 𝐶𝑏 𝑇𝑠 + 𝐶𝑏 𝑇𝑏 𝑘 : standard score 𝑇𝑠 : Sample Counting Time 𝑇𝑏 : Background Counting Time 𝐶𝑏 : Background Count Rate & Quantum NQe Nuclear Engineering Department • 𝑀𝐷𝐴 = 𝑀𝐷𝐶𝑅 ×𝐹 𝐸𝑓𝑓 ×𝑉(𝐿) −1 𝐹 : 4.50 × 10 pCi/dpm 𝐸𝑓𝑓 : Counting efficiency 𝑉(𝐿) : Volume of Sample 40 NENS Nuclear Energy Environment and Nuclear Security Laboratory Results Cases Cover thickness Ignoring -> MLE (29.11->14.13 mrem/yr) More than 3m DL -> MLE (15.99->14.13 mrem/yr) More than 3m 1/2 DL -> MLE (14.15->14.13 mrem/yr) 13.5cm Table 7. Cover thickness calculated to show the difference between the each method & Quantum NQe Nuclear Engineering Department 41 NENS Nuclear Energy Environment and Nuclear Security Laboratory Introduction – ROS • 𝑝𝑒𝑖 = 𝑝𝑒𝑗+1 + 𝐴𝑗 𝐴𝑗 +𝐵𝑗 [1 − 𝑝𝑒𝑗+1 ] 𝐴𝑗 = the number of observations detected between the jth and (j+1)th detection limits 𝐵𝑗 = the number of observations, censored and uncensored below the jth detection limit The number of nondetects below the jth detection limit is defined as 𝐶𝑗 : 𝐶𝑗 = 𝐵𝑗 − 𝐵𝑗−1 − 𝐴𝑗−1 • Calculating the plotting position: For observed values 𝑖 𝑝𝑑𝑖 = (1 − 𝑝𝑒𝑗 ) + [𝑝𝑒𝑗 − 𝑝𝑒𝑗+1 ] 𝐴𝑗 + 1 For censored observations 𝑖 𝑝𝑐𝑖 = ∗ [1 − 𝑝𝑒𝑗 ] 𝐶𝑗 + 1 & Quantum NQe Nuclear Engineering Department 42 NENS Nuclear Energy Environment and Nuclear Security Laboratory Case study • The survey consisted of Grid box No.1 and Grid box No.2, each having 30 data points measuring the concentration of U-238 and K-40, in the same area. • In Grid box No.1, 8 data points are below the detection limit for U-238, and 17 for K-40. Grid box No.1 U-238 (8/30) K-40 (17/30) Fig. 3. Schematic diagram of Grid box No.1 & Quantum NQe Nuclear Engineering Department U-238 K-40 MDA Minimum (Bq/g) 0.00997 0.00369 MDA Maximum (Bq/g) 0.0953 0.0118 Table 3. MDA of U-238 and K-40 in Grid box No.1 43 NENS Nuclear Energy Environment and Nuclear Security Laboratory Case study • In Grid box No.2, 10 data points are below the detection limit for U-238, and 9 for K-40. Grid box No.2 U-238 (10/30) K-40 (9/30) Fig. 4. Schematic diagram of Grid box No.2 & Quantum NQe Nuclear Engineering Department U-238 K-40 MDA Minimum (Bq/g) 0.0111 0.00339 MDA Maximum (Bq/g) 0.109 0.0126 Table 4. MDA of U-238 and K-40 in Grid box No.2 44