IRPhEP Database and Analysis Tool (IDAT)



Similar documents
Evaluation of Sodium-cooled Fast Reactor Neutronic Benchmarks

CRITICALITY ACCIDENT ALARM SYSTEM MODELING WITH SCALE

INTRODUCTION. The ANSWERS Software Service WIMS AEA Technology plc

DEVELOPMENT OF A DYNAMIC SIMULATION MODE IN SERPENT 2 MONTE CARLO CODE

. Space-time Analysis code for AHWR

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

COMPLETE USER VISUALIZATION INTERFACE FOR KENO

How To Understand The Sensitivity Of A Nuclear Fuel Cask

Nuclear Science and Technology Division (94) Multigroup Cross Section and Cross Section Covariance Data Visualization with Javapeño

SCDAP/RELAP5-3D : A State-of-the-Art Tool for Severe Accident Analyses

Introduction to Nuclear Fuel Cycle and Advanced Nuclear Fuels

List of Papers. This thesis is based on the following papers, which are referred to in the text by their Roman numerals.

Uncertainty Estimation of Target System Multiplication Factors with the new COMMARA Covariance Matrix

Determination of the Comsumption Rate in the Core of the Nigeria Research Reactor-1 (NIRR-1) Fuelled with 19.75% UO 2 Material

Software support. Overview Process step: Selection and sizing. Process step: Engineering design. Process step: Ordering in the Online Shop

CASL: Consortium for the Advanced Simulation of Light Water Reactors: Program Update

Jan Zdebor David Pavlis. ŠKODA JS a.s. and its Cooperation with Czech Universities

BWR Description Jacopo Buongiorno Associate Professor of Nuclear Science and Engineering

Sensitivity- and Uncertainty-Based Criticality Safety Validation Techniques

BEST-ESTIMATE TRANSIENT ANALYSIS WITH SKETCH-INS/TRAC-BF1, ASSESSMENT AGAINST OECD/NEA BWR TURBINE TRIP BENCHMARK ABSTRACT

DOE s Fuel Cycle Technologies Program - An Overview

Abstract. Adaptive simulation (AS) is an algorithm utilizing a regularized least squares methodology

IN REACTOR PHYSICS ANALYSIS

Dynamic Load Balancing of Parallel Monte Carlo Transport Calculations

Current Engineering and Design Activities at Los Alamos National Laboratory Supporting Commercial U.S. Production of 99Mo without the Use of HEU

The Fuel Cycle R&D Program. Systems Analysis

Interoperable Learning Leveraging Building Information Modeling (BIM) in Construction Management and Structural Engineering Education

Fukushima Fukushima Daiichi accident. Nuclear fission. Distribution of energy. Fission product distribution. Nuclear fuel

Configuring SharePoint 2013 Document Management and Search. Scott Jamison Chief Architect & CEO Jornata scott.jamison@jornata.com

ELPUB Digital Library v2.0. Application of semantic web technologies

Data Analysis for Yield Improvement using TIBCO s Spotfire Data Analysis Software

Current Standard: Mathematical Concepts and Applications Shape, Space, and Measurement- Primary

Preliminary validation of the APROS 3-D core model of the new Loviisa NPP training simulator

VARIANCE REDUCTION TECHNIQUES FOR IMPLICIT MONTE CARLO SIMULATIONS

ElegantJ BI. White Paper. Key Performance Indicators (KPI) A Critical Component of Enterprise Business Intelligence (BI)

V K Raina. Reactor Group, BARC

Internet accessible facilities management

WORLD ASSOCIATION OF NUCLEAR OPERATORS. Performance Indicators

Chapter ML:XI (continued)

Flow distribution and turbulent heat transfer in a hexagonal rod bundle experiment

Categorisation of Active Material from PPCS Model Power Plants

NURESAFE EUROPEAN PROJECT Second General Seminar

Qualification of Thermal hydraulic codes within NURESIM D. Bestion (CEA, France)

A Comprehensive Set of Image Quality Metrics

Introductions: Dr. Stephen P. Schultz

NEUTRON NOISE CALCULATION IN A LARGE SFR CORE AND ANALYSIS OF ITS PROPERTIES

DOE FUNDAMENTALS HANDBOOK

UNIVERSITY OF BOLTON SCHOOL OF ENGINEERING MS SYSTEMS ENGINEERING AND ENGINEERING MANAGEMENT SEMESTER 1 EXAMINATION 2015/2016 INTELLIGENT SYSTEMS

Course Overview Lean Six Sigma Green Belt

Christopher M. Perfetti, PhD

DEMONSTRATION ACCELERATOR DRIVEN COMPLEX FOR EFFECTIVE INCINERATION OF 99 Tc AND 129 I

A MTR FUEL ELEMENT FLOW DISTRIBUTION MEASUREMENT PRELIMINARY RESULTS

Piotr Tofiło a,*, Marek Konecki b, Jerzy Gałaj c, Waldemar Jaskółowski d, Norbert Tuśnio e, Marcin Cisek f

Dynamic Behavior of BWR

USING DASHBOARDS AND REPORTS V1.0

Self-adjusting Importances for the Acceleration of MCBEND

Report on heat production during preliminary tests on the Rossi Ni-H reactor.

Alignment and Preprocessing for Data Analysis

University of Cambridge: Programme Specifications MASTER OF PHILOSOPHY IN NUCLEAR ENERGY

Conservative approach for PWR MOX Burnup Credit implementation

Programme Specification and Curriculum Map for BA (Hons) Fashion Design

Business Intelligence & Product Analytics

Development of Monitoring and Analysis Tools for the Huawei Cloud Storage

University of Cambridge: Programme Specifications MASTER OF PHILOSOPHY IN ENGINEERING FOR SUSTAINABLE DEVELOPMENT: PROGRAMME SPECIFICATION

British Nuclear Group Reactor Sites Chemistry Issues NuSAC SCR Meeting - April 4 th 2006

Spent Fuel Project Office Interim Staff Guidance - 17 Interim Storage of Greater Than Class C Waste

Technical Challenges for Conversion of U.S. High-Performance Research Reactors (USHPRR)

Keep managers better informed on their areas of responsibility and highlight the issues that require their attention with dashboards!

IDEAS Property Clerk Enterprise Property Management Accounting Software. IDEAS Software

Data Mining and Visualization

Long Term Operation R&D to Investigate the Technical Basis for Life Extension and License Renewal Decisions

Esri Maps for Business Intelligence (BI)

Nuclear Design Practices and the Case of Loviisa 3

JRefleX: Towards Supporting Small Student Software Teams

IDL. Get the answers you need from your data. IDL

Global Nuclear Energy Partnership Technology Demonstration Program

UTILIZING RESEARCH REACTORS FOR EDUCATION AND TRAINING: INTERNET REACTOR LABORATORY

-- Martensdale-St. Marys Community School Math Curriculum

ElegantJ BI. White Paper. Considering the Alternatives Business Intelligence Solutions vs. Spreadsheets

Rules & Regulations Handbook

Polyvalent fuel treatment facility (TCP) : shearing and dissolution of used fuel at La Hague facility

Plutonium vs. Uranium: The Road Less Traveled. In a world where nuclear proliferation may no longer be held back by the guise of antiproliferation

TSRR: A Software Resource Repository for Trustworthiness Resource Management and Reuse

Kodo - Cross-platform Network Coding Software Library. Morten V. Pedersen - Aalborg University / Steinwurf ApS mvp@es.aau.dk

Transcription:

IRPhEP Database and Analysis Tool (IDAT) http://www.oecd-nea.org/science/ Ian Hill December 2 th 2011

Outline ICSBEP, IRPhEP (quick reminder) and the Database + Data Analysis Tool ICSBEP + DICE (2 Slides) IRPhEP overview (1 Slide) IRPhEP Database and Analysis Tool Design (5 Slides) Differences between ICSBEP/DICE requirements Inclusion of measured + calculated values Features (6 Slides) Demonstration of prototype Implemented and planned features Possible relationship with SG33, uncertainty+sensitivities

DatabaseInternationalCriticalityExperiments(est. 2001) Efficiently search the ICSBEP handbook. Alternative was opening hundreds of pdfs. Search based on keyword, country, spectra, fuel type, materials, etc. Allows visual trending of the data. Can visually depict the information content of the DVD, identify relevant experiments. Contains calculated quantities; 299 group neutron spectra data, neutron balance data, sensitivity data. ICSBEP Number of Cases vs Year ~600 Evaluations 3932 4064 4207 4283 4405 2176 2417 2645 2884 3073 3332 3603 1751 983 1327 406 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010

DICE: Features Compare spectra Compare capture + fission rate Some correlation data VIBE plugin ENDF/B-VII The use of VIBE as a plug-in module to DICE to access and interpret sensitivity data is described. In this initial release of VIBE within DICE, VIBE can identify sensitivity data and group collapse the data into a table, where the values can be sorted and filtered to identify experiments that are the most similar to a targeted application system in terms of sensitivity data. VIBE can then retrieve information about the selected experiments from the DICE database to provide the physical characteristics of the benchmarks H1 0.722101 (ABBN) H1 0.724974 +/-0.000756 (TSUNAMI3D)

#Evaluations #Data Points IRPhEP Information Content 10+ types of measurements (~40 evaluations in 2010) Relevant points when creating a database Lower frequency=difficult to derive standard for measurements with few data points CRIT,SPEC,RRATE measurements given priority. Next most common are REAC,COEF measurements Less than 5 evaluations contain SUB,KIN,POWDIS,ISO,MISC measurements (Less need to search, or trend these measurements) Each of these measurements includes an evaluation of the experimental uncertainties associated with that measurement 40 35 30 25 20 15 10 5 0 2010 Handbook 9000 8000 7000 6000 5000 4000 3000 2000 1000 0 DIMPLE 2010 Handbook

Why Make a Database? Levels of data preservation 1. Archive 2. Compilation 3. Interpretation + Review Handbook 4. Database Extracting, comparing and trending, example C/E k-eff vs. Data Library Limitations of Handbook Difficult to search, opaque information content Cannot trend across evaluations Adding information requires new revisions Detailed Description Evaluation of Experimental Data Handbook Reactor Type BWR Drafts FUND GCFR GCR HWR LMFR LWR MISC MSR PWR RBMK VVER Sections Benchmark Specification Measurements Results of Sample Calculation Correlation Matrix CRIT BUCK SPEC REAC COEF KIN RRATE POWDIS ISO MISC

Database Construction: CRIT,SPEC,RRATE done. In progress REAC,COEF. Read Evaluations. Enter Key data into EXCEL, observe trends and commonality. Prioritize based on information content and user interest. Create key parameters list, for each measurement + calculation. Standardize format (X,Y,Z coordinates in cm, Measured, Calculated, Percent difference for Error) Set up an EXCEL sheet to prepare loading of a RDBMS database. Extract data from document, transform into the standard format. K-eff, Averaged C/E

Next Step: Add Calculated Values(what would we like to store) Calculated data in DICE: (~90 %) Spectra, 3 Group Flux+Reactions, Neutron balance, (~10 %) Nuclear data sensitivity WISH-LIST (Initially no data available!) Neutron Balance Sensitivity to Nuclear Data Flux and Reaction Spectrums Spatial Flux and Reactions Correlation Coefficients Uncertainty Information How to obtain calculated results? 1. Use models in handbook 2. Ask users to contribute 3. In house model adapting and creation Some Numbers(2010 IRPhEP Handbook) Some evaluations have models 22 MCNP 6 KENO (keno+mmk-keno) Other-MVP, CITATION etc % Evaluations Models Run: ~50 % (MCNP+Added PRINT cards+meshtally) % Cases Models Run: ~30 %

New to the IRPhEP Database User Interface Tool 1. MESH Tool 2. Plot features 3. Find Similar Option 4. Balance Computations

Development: MeshViewer Tool (N.Soppera) IRPhEP Experiments are typically more complex Visualization helps the user understand the reactor and often the experiments. Often will return to the evaluation to explain something they see. Knowledge Management! a)flux b)capture Rates c)fission Rates d)scattering Rates e)neutron Spectra Can also perform math operations. Useful when constructing a benchmark model in a different core, or observing the impact of removing control rods. Works with MCNP, SERPENT, KENO (accepting other mesh formats!) Considering overlaying plot on geometry.perhaps too much?

New Plotting Features Can collapse data over many measurements. Convey big picture, allow user to subsequently drill down to more detail. Particularly useful for reaction rate measurements. Additional work needed on collapsing methods (weighted average, correlations). C/E C/E

Search Similar Option Why: Inter and intra comparison of experiments Designer/Nuclear data validator can search for experiments which mimic the desired application. Examples: Similar Spectrum (done) Similar Balance (done) Similar Sensitivity (no sensitivity data) Similar Uncertainty (uncertainties recently added) Correlations of uncertainties of measurements Correlations of uncertainties due to nuclear data

For Neutron Balance Files Similarity based on Euclidean Distance 1 ( p 1 q ) 1 2 ( p 2 0.5 2 q p ) 2 2 0.5... ( p q 0.5 N q N ) 2 N=Isotope Future Application: Use similarity metrics to compare results from different nuclear data libraries and codes. Possible links/synergy with uncertainty information?

Plotting Neutron Balance Files

Uncertainty (pcm) Uncertainties Short + Medium + Long Term Extract Uncertainties IRPhEP (Name of Perturbation, parameter base value, parameter units, parameter uncertainty, delta k) GROUP Geometry Composition Experimental Modeling 200 150 100 50 0 Eval #1 Eval #2 Eval #3 Modeling Composition Geometry Experimental GROUP Fuel Cladding Coolant/Moderator Core Evaluation ID Cross Check Composition Uncertainties Against Sensitivities Trend Uncertainties vs. Other Database Parameters Feedback Guidance to Future Evaluators Compare Experimental+ Nuclear Data+ Modeling Uncertainties to actual C/E Compare(2) Possible sanity check cross check against difference in balance files upon direct perturbations

Sensitivities Medium + Long Term Collect Sensitivities (Accept various formats likely. Possibility to impose format, but reluctant to dissuade users) Allow user to link to covariance data file + compute nuclear data uncertainty Allow users to perturb reactions, observe impact on plots Implement a generalized least squares option to automatically adjust data Link sensitivities to Mesh Viewer Tool Compare across codes, libraries, models

Conclusion NEA/OECD have a long history of collecting and leveraging benchmark data ICSBEP (1992/1995) DICE (2001) IRPhEP (2000) Done: IDAT prototype (2012) [A technical advisory group being formed for IDAT] Initial stage of database and analysis tool Most of the information content has been entered Design of prototype user interface In Progress: New Plotting Features, adding SPEC,REAC,COEF data Error Checking Assemble Spectra and Neutron balance data Compile uncertainty data. Compute or collect sensitivity data. Priority list of features (Eventually public?) Soon: Additional measurements Upgrade to 2011 data Feedback Welcome! Ian.Hill@oecd.org

Acknowledgement Work has been made possible by the generous voluntary financial contributions of Japan N.Soppera, M.Bossant