United States Nuclear Regulatory Commission 1 Simulation Modeling: A Reviewer’s Perspective David W. Esh 1 and Cynthia S. Barr 2 Division of Waste Management.

Slides:



Advertisements
Similar presentations
Use of reference biospheres to prove long-term safety of repositories for radioactive waste Workshop, Berlin, August 2008.
Advertisements

Design of Experiments Lecture I
Lesson 3 ODOT Analysis & Assessment. Analysis & Assessment Learning Outcomes As part of a small group, apply the two- part analysis by generating exposure-
Near Surface Disposal Facilities
A U.S. Department of Energy Office of Science Laboratory Operated by The University of Chicago Office of Science U.S. Department of Energy Risk-Based Regulation.
The System and Software Development Process Instructor: Dr. Hany H. Ammar Dept. of Computer Science and Electrical Engineering, WVU.
EVALUATION OF METHODS AND MODELS USED TO PREDICT WATER QUALITY AT HARDROCK MINE SITES: SOURCES OF UNCERTAINTY AND RECOMMENDATIONS FOR IMPROVEMENT Ann Maest,
Constructing Conceptual Site Model (CSM) Diagrams using the Simulation Editor EXAMPLE Constructing Conceptual Site Model (CSM) Diagrams using the Simulation.
1 Approved for unlimited release as SAND C Verification Practices for Code Development Teams Greg Weirs Computational Shock and Multiphysics.
GoldSim 2006 User Conference Slide 1 Vancouver, B.C. The Submodel Element.
Marakas: Decision Support Systems, 2nd Edition © 2003, Prentice-Hall Chapter Chapter 4: Modeling Decision Processes Decision Support Systems in the.
Environmental Health XIV. Standards and Monitoring Shu-Chi Chang, Ph.D., P.E., P.A. Assistant Professor 1 and Division Chief 2 1 Department of Environmental.
The Calibration Process
Software maintenance Managing the processes of system change.
AUDIT PROCEDURES. Commonly used Audit Procedures Analytical Procedures Analytical Procedures Basic Audit Approaches - Basic Audit Approaches - System.
Challenges in developing a Safety Case WG5. How to Develop a Safety Case SC can be a tool for providing information to stakeholders other than regulators.
Radionuclide dispersion modelling
EGU General Assembly 2007 Neptune and Company, Inc. Los Alamos, NM, USA A Systems Modeling Approach for Performance Assessment of the Mochovce National.
Safety Assessment Methodologies and Implementation of Monitoring and Control Programmes Dr. Japie van Blerk AquiSim Consulting (Pty) Ltd Wednesday, 24.
Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy’s National Nuclear.
Contaminated land: dealing with hydrocarbon contamination Assessing risks to human health.
1 Validation & Verification Chapter VALIDATION & VERIFICATION Very Difficult Very Important Conceptually distinct, but performed simultaneously.
1 Performance Evaluation of Computer Networks: Part II Objectives r Simulation Modeling r Classification of Simulation Modeling r Discrete-Event Simulation.
FRAMES-2.0 Workshop U.S. Nuclear Regulatory Commission
FIRE PROTECTION TOPICS OF INTEREST Defense Nuclear Facilities Safety Board.
Performance Assessment Issues in Waste Management and Environmental Protection Annual Meeting of the Baltimore-Washington Chapter of the Health Physics.
Chapter 6 : Software Metrics
Creating a Shared Vision Model. What is a Shared Vision Model? A “Shared Vision” model is a collective view of a water resources system developed by managers.
1 The U.S. NRC’s Reactor Certification and Licensing Process – Meeting the Challenge? Commissioner Peter B. Lyons U.S. Nuclear Regulatory Commission 15.
Multimedia Assessment for New Fuels: Stakeholders’ Meeting September 13, 2005 Sacramento, CA Dean Simeroth, California Air Resources Board Dave Rice, Lawrence.
Nicolas Solente Workshop on Regulatory Requirements to Ensure Safe Disposal of Disused Sealed Sources for Operators and Regulators Amman, JORDAN 7-11 April.
The System and Software Development Process Instructor: Dr. Hany H. Ammar Dept. of Computer Science and Electrical Engineering, WVU.
MODULE “PREPARING AND MANAGEMENT OF DOCUMENTATION” SAFE DECOMMISSIONING OF NUCLEAR POWER PLANTS Project BG/04/B/F/PP , Programme “Leonardo da Vinci”
56th Regular Session of the IAEA General Conference
Sensitivity and Importance Analysis Risk Analysis for Water Resources Planning and Management Institute for Water Resources 2008.
David G Bennett December 2014
Developing a Data Base Supporting Very long- term Storage of Spent Nuclear Fuel R E Einziger, Ph.D., E. Benner, and C. Regan Spent Fuel Storage & Transportation.
Specific Safety Requirements on Safety Assessment and Safety Cases for Predisposal Management of Radioactive Waste – GSR Part 5.
1.Issues concerning the Inventory 2.Issues concerning Gases 3.Site considerations 4.Construction Issues 5.Waste Packaging.
International Atomic Energy Agency Definition and overview of required safety documentation (e.g., safety case and safety assessment) Phil Metcalf Workshop.
Argonne National Laboratory Experience and Perspectives on Environmental Remediation Karen P. Smith Environmental Science Division Argonne National Laboratory.
-1- UNRESTRICTED / ILLIMITÉ Demonstrating the Safety of Long-Term Waste Management Facilities Dave Garrick 2015 September.
AGU Fall 2006 Meeting Neptune and Company, Inc. Radioactive Waste Disposal in Hydrologically-Challenged Environments: Opportunities for Waste Disposal.
RLV Reliability Analysis Guidelines Terry Hardy AST-300/Systems Engineering and Training Division October 26, 2004.
International Atomic Energy Agency Regulatory Review of Safety Cases for Radioactive Waste Disposal Facilities David G Bennett 7 April 2014.
Exposure Assessment for Health Effect Studies: Insights from Air Pollution Epidemiology Lianne Sheppard University of Washington Special thanks to Sun-Young.
An Introduction To Modeling of Surface Waters For TPDES Permits Mark A. Rudolph, P.E. TCEQ Water Quality Division.
Safety-related Issues for the Disposal of Intermediate Level Waste (ILW) Dr. Jürgen Wollrath Federal Office for Radiation Protection (BfS) Department Safety.
1 Modeling Complex Systems – How Much Detail is Appropriate? David W. Esh US Nuclear Regulatory Commission 2007 GoldSim User Conference, October 23-25,
1 BROOKHAVEN SCIENCE ASSOCIATES NSLS-II Shielding Workshop R. Casey Activation Issues for NSLS-II March 28, 2007.
Building Valid, Credible & Appropriately Detailed Simulation Models
Presentation for Office of Surface Mines on Potential Use of the Leaching Environmental Assessment Framework to enhance source terms for use of CCRs in.
Risk CHARACTERIZATION
Use and Conduct of Safety Analysis IAEA Training Course on Safety Assessment of NPPs to Assist Decission Making Workshop Information IAEA Workshop Lecturer.
United States Nuclear Regulatory Commission NRC’s Risk-Informed and Performance- Based Approach to Decommissioning DOE Workshop on Risk-Based End States.
Software Development Module Code: CST 240 Chapter 6: Software Maintenance Al Khawarizmi International College, AL AIN, U.A.E Lecturer: Karamath Ateeq.
The Safety Case Radioactive Waste and Spent Fuel Management Unit
HOW MUCH RADIOACTIVE WASTE COULD POTENTIALLY BE IMPORTED INTO TEXAS
Radiological impacts from nuclear industrial facilities on the public and the environment : Their magnitude and the next 50 years forecast Sylvain Saint-Pierre.
-EL ABBARI Younes, FADIL Najib (CNESTEN) -SADIQ Younes (AMSSNuR)
Proposed Revisions to 10 CFR Part 61
South Carolina Perspective on Part 61 Proposed Revisions
The Calibration Process
Software Project Planning &
Safety Case Components and Documentation
Revisions to the Concentration Averaging and Encapsulation Branch Technical Position A. Christianne Ridge Division of Decommissioning, Uranium Recovery,
Plenary Meeting of the Network on  Environmental 
Building Valid, Credible, and Appropriately Detailed Simulation Models
What to look at in fire engineering analysis
Modeling Water Treatment Using the Contaminant Transport Module
Presentation transcript:

United States Nuclear Regulatory Commission 1 Simulation Modeling: A Reviewer’s Perspective David W. Esh 1 and Cynthia S. Barr 2 Division of Waste Management and Environmental Protection Presented to: 2006 International GoldSim User Conference, Vancouver, BC, June 6 th -7 th, 2006 Contact info: 1 (301) , 2 (301) ,

United States Nuclear Regulatory Commission 2 Simulation modeling is increasingly being used in problem solving and decision making. Simulation models are reviewed by the model developers, regulators, and other stakeholders. The objective of the review process is to develop confidence in the model results and decisions based on those results.

United States Nuclear Regulatory Commission 3 Presentation Outline Reviewing Simulation Models –Reviewability –Complexity –Support –Other considerations Identifying Risk Significant Components of Simulation Models –Risk informing –Determining risk significant components

United States Nuclear Regulatory Commission 4 Simulation Modeling: Reviewability Simulation models must be able to be independently reviewed and understood. –Consider objective of the model –Consider audience –Models don’t make decisions, humans make decisions Documentation of the modeling is as important as the modeling itself. The analysis and documentation must be transparent and traceable. Data should be traceable to the source to facilitate the review of data validity.

United States Nuclear Regulatory Commission 5 Simulation Modeling: Reviewability The modeling and documentation should be consistent. Documentation and explanation (and therefore cost) increases with model complexity. A model that is not understood is unlikely to be accepted. Consider review effort: –100,000 lines of FORTRAN code compared to a 100 element visual simulation model? GoldSim models are inherently easier to review.

United States Nuclear Regulatory Commission 6 Example of a complex site

United States Nuclear Regulatory Commission 7 Simulation Modeling: Complexity Review effort increases exponentially with increasing model complexity. Model complexity should be commensurate with available supporting information. However, the analysis approach should test whether additional complexity may have a significant impact on the model results. Model building is a dynamic process in itself. If complexity is added to a model and found not to have a significant influence on the results (either favorable or unfavorable), it should be removed.

United States Nuclear Regulatory Commission 8 Simulation Modeling: Complexity Complex does not necessarily mean better. However, sometimes complexity is unavoidable and necessary. Example: –INTRAVAL, Synthetic Migration Experiment, Phase 1 Case 6 [copies of the report are available from the Swedish Nuclear Power Inspectorate (SKi)] –A modeler who used hand calculations to estimate fracture properties did as well, and in some cases considerably better, at predicting the experimental results than much more sophisticated calculations (e.g., geospatial techniques).

United States Nuclear Regulatory Commission 9 Simulation Modeling: Support Model support is arguably the most essential element to successful simulation modeling. Simulation modeling should have support, at a minimum, in the form of verification and validation: –Verification – Solving the equations right –Validation – Solving the right equations A variety of elements can be part of the model support process, including the following: internal review (QA), independent external review, documentation of verification efforts, and a multi-faceted validation effort.

United States Nuclear Regulatory Commission 10 Simulation Modeling: Support Simulation modeling that allows for the independent review and understanding of intermediate outputs is strongly encouraged. Documentation and openness about shortcomings of the modeling generally increases confidence for the reviewer. Natural and dynamic systems can be inherently difficult to predict. Simulation modelers, by their nature, are biased to being overconfident in their ability to predict a system. Example:Causal inference

United States Nuclear Regulatory Commission 11 Simulation Modeling: Support Consider transient nature of the system and ability of short- term data to validate model that makes long-term predictions.

United States Nuclear Regulatory Commission 12 Simulation Modeling: Other Considerations Consideration of uncertainty and variability is typically essential for successful simulation modeling. Understanding the impact of uncertainty can be difficult using sensitivity analysis of a deterministic model when the system being modeled is complex. When model support is limited, a simple, highly-uncertain simulation model is generally preferable to a complex, deterministic model.

United States Nuclear Regulatory Commission 13 Developing and Presenting Risk Information To the extent practical, the simulation model development and subsequent analysis process should have an objective of identifying risk information. Risk is defined here to be those things most likely to impact the decision. For example, in problems that NRC reviews, there may be 500 parameters in the analysis: –The reviewer wants to focus on those 10 to 20 most likely to impact the decision. –The analyst should want to identify the same parameters, so they can increase the support for those parameters.

United States Nuclear Regulatory Commission 14 Developing and Presenting Risk Information There are many methods for determining important parameters and uncertainties (e.g., regression analysis, genetic algorithms, parameter trees). Our experience is that one method is not the best, and usually multiple methods should be used. The analyst should develop an understanding of the model, which can be as important as quantitative analysis techniques. The understanding of the analyst can be very important to adequately performing the analysis.

United States Nuclear Regulatory Commission 15 Developing and Presenting Risk Information The reviewer may not have the time to review all of the information available. Produce the most convincing argument (with the least amount of information)!

United States Nuclear Regulatory Commission 16 An independent PA model was used to develop risk insights for the review of the Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) NRC staff typically uses independent performance assessment (PA) models to develop risk insights In this context, a performance assessment is a model to project the long-term (e.g., thousands of years) performance of natural and engineered systems for the disposal of radioactive waste. Developing Risk Insights: Example

United States Nuclear Regulatory Commission 17 Developing Risk Insights: Example 49 operational high-level waste tanks at SRS The Department of Energy (DOE) plans to: –Remove salt waste from the tanks –Mix treated liquid salt waste with dry ingredients to create a cementitious wasteform called “saltstone” –Dispose of approximately 5 million cubic meters of saltstone in concrete vaults on site

United States Nuclear Regulatory Commission 18 Developing Risk Insights: Example NRC staff had to review a PA model initially developed in 1992, updated in 1998, and a supporting analysis performed in The DOE analysis was deterministic, performed with a variety of software products in which the outputs were manually transferred between programs. The analysis was documented in a 1992 document of over 700 pages, a few main supporting documents of many hundred pages each (and many hundred references). There was no clear linkage of the analysis, the data used, and the documentation.

United States Nuclear Regulatory Commission 19 Developing Risk Insights: Example NRC staff, in this case and commonly, does not have an unlimited amount of time to perform the review. What do you review? How do you review it? What are the essential questions to ask? What is driving the results of the analysis? What is the impact of uncertainty?

United States Nuclear Regulatory Commission 20 Developing Risk Insights: Example Model developed using GoldSim Software: –Probabilistic assessment –Specialized elements facilitate radionuclide transport modeling –1150 elements, more than 300 stochastic elements Submodels included: –Degradation of engineered cap –Oxidation of saltstone –Physical degradation of saltstone –Release of radioactive material –Transport in unsaturated and saturated subsurface zones as well as surface water –Exposure pathways –Dose assessment

United States Nuclear Regulatory Commission 21 Developing Risk Insights: Example Preliminary results were sensitive to wasteform degradation assumptions Preliminary results indicated need to model degradation and oxidation as a function of time Model refined to include submodels of: –Grout oxidation –Physical degradation of wasteform Simulation modeling using risk insights is typically iterative.

United States Nuclear Regulatory Commission 22 Developing Risk Insights: Example Oxidized thickness Degraded thickness saltstone wasteform soil Number of half cells modeled depends on user-defined fracture spacing intact oxidized degraded

United States Nuclear Regulatory Commission 23 Risk Insights Example – Analysis Approach Run probabilistic base-case model Develop confidence in model –Individual realizations physically reasonable –Results insensitive to time-stepping and number of realizations Run genetic analysis of base-case probabilistic results using Neuralworks Predict ® Limit number of stochastic variables Re-run genetic analysis Evaluate alternate cases

United States Nuclear Regulatory Commission 24 Uncertainty Analysis with Genetic Algorithms for the Base Case, Using a Shortened Variable List Variable Name Description Importance Factor GW_flow Average Darcy velocity of fluid in the saturated zone transport pipe. Influences dilution and transport times Fracture_spacing Average spacing of fractures in the wasteform. Influences the amount of oxidation and degradation during the simulation period and the diffusive path length of contaminants to the fractures Water_intake Consumption rate of drinking water. Directly influences the drinking water dose Bound_waste_deg_rate Rate at which contaminants are available for release and transport. Conceptually represents dissolution of the wasteform Mg_conc Concentration of Mg in the fluids contacting the wasteform. Influences the amount of degradation predicted to occur during the simulation period Infiltration_rate Rate of infiltration of water into the subsurface. Influences the release and transport of contaminants from the wasteform. 0.71

United States Nuclear Regulatory Commission 25 Risk Insights Example – Conclusions Risk insights (in this case developed by the reviewer) were used to focus the review on key elements of the simulation model. Requests for additional information were reduced (compared to if risk insights were not used). A simple, highly uncertain model was refined and the complexity increased based on initial analyses. By identifying and emphasizing risk-significant elements of the modeling, the confidence in the decision should be enhanced for all stakeholders (e.g., that public health and safety will be protected).

United States Nuclear Regulatory Commission 26 Conclusions The reviewability of the model should be considered when a simulation model is developed. Transparent and traceable analysis and documentation can be as important as the details of the modeling. Model complexity should be increased as needed, and removed if it is not materially affecting the decision. Model support is essential to validating a model and increasing confidence in model results. Developing and presenting risk information can accelerate the process of achieving credibility of the modeling and developing confidence in the resultant decisions.