INGSM-14, 16 th -18 th September 2013, Seattle, USA Development of a stress-based emulator for AGR moderator bricks M Fahad †, K McNally ‡, G Hall †, BJ.

Slides:



Advertisements
Similar presentations
Insert Date HereSlide 1 Using Derivative and Integral Information in the Statistical Analysis of Computer Models Gemma Stephenson March 2007.
Advertisements

Running a model's adjoint to obtain derivatives, while more efficient and accurate than other methods, such as the finite difference method, is a computationally.
Nuclear Graphite Research Group University of Manchester, UK
1 INGSM 14, Seattle NOT PROTECTIVELY MARKED BEG/FORM/COMM/026A REV 007 Graphite Core Inspection, Measurement of Brick Stress M Brown – EDF-E E Kingston.
Designing Ensembles for Climate Prediction
The AGC-1 Creep Experiment - Results and Analysis INGSM-15 HANGZHOU, CHINA Sept 15-18, 2015 Tim Burchell Fusion Materials & Nuclear Structures Group Materials.
Presented by: Nassia Tzelepi Progress on the Graphite Crystal Plasticity Finite Element Model (CPFEM) J F B Payne L Delannay, P Yan (University of Louvaine)
Aug 9-10, 2011 Nuclear Energy University Programs Materials: NEAMS Perspective James Peltz, Program Manager, NEAMS Crosscutting Methods and Tools.
Density-Based Model of Bending Strength for AGR Graphites Irradiated in Oxidising Environments Ernie D. Eason Modeling & Computing Services Boulder, Colorado,
MTR Project BLACKSTONE Tjark van Staveren, NRG Steven Knol, NRG Matthew Brooking, EDF Energy September 18, 2013.
Sensitivity Analysis In deterministic analysis, single fixed values (typically, mean values) of representative samples or strength parameters or slope.
RaDIATE Progress Meeting, May 2013 Graphite progress update BJ Marsden and G Hall Nuclear Graphite Research Group, School of MACE, The University of Manchester.
MTR Project ACCENT T.O. van Staveren, NRG A.J. de Koning, NRG M. Davies, Frazer Nash Consultancy September 18, 2013.
Training Manual Aug Probabilistic Design: Bringing FEA closer to REALITY! 2.5 Probabilistic Design Exploring randomness and scatter.
Reliability Prediction of a Return Thermal Expansion Joint O. Habahbeh*, D. Aidun**, P. Marzocca** * Mechatronics Engineering Dept., University of Jordan,
Finite Element Method in Geotechnical Engineering
1 KNOO Annual Meeting 2009 CFD analysis of Fuel Rod Bundles S. Rolfo D. Laurence School of Mechanical, Aerospace & Civil Engineering (MACE) The University.
Ken Powell and Ryan McClarren CRASH Review, October 2010 CRASH Students and Courses.
MCE 561 Computational Methods in Solid Mechanics
Evaluation and Comparison of Fracture Behavior of Selected Nuclear Graphite by Small Size SENB Specimens Se-Hwan Chi. Ph. D. 15 th International Nuclear.
Mechanical strength testing of irradiated HTR graphite grades M.C.R. Heijna, J.A. Vreeling NRG, Petten The Netherlands INGSM September 2013 Seattle.
Copyright © Toyo Tanso Co., Ltd. All Rights Reserved TECS Irradiation Program for IG-110 and IG-430 Graphite for Evaluation of High Fluence Behavior.
Outline Lesson 1. Introduction to ANSYS Lesson 2. Basics Lesson 3. Solution phases Lesson 4. Modeling Lesson 5. Material Lesson 6. Loading Lesson 7. Solution.
Engineering Doctorate – Nuclear Materials Development of Advanced Defect Assessment Methods Involving Weld Residual Stresses If using an image in the.
Random Finite Element Modeling of thermomechanical behavior of AGR bricks Jose David Arregui Mena, Louise Lever, Graham Hall, Lee Margetts, Paul Mummery.
Gwangju Institute of Science and Technology Intelligent Design and Graphics Laboratory Multi-scale tensor voting for feature extraction from unstructured.
Graphite Component Assessment for TMSR Samantha Yong, Derek Tsang, Maoyuan Cai.
Development of New Techniques for AGR Graphite Presented by: Nassia Tzelepi.
Modeling and Validation of a Large Scale, Multiphase Carbon Capture System William A. Lane a, Kelsey R. Bilsback b, Emily M. Ryan a a Department of Mechanical.
Andrea Salvini, CERN, L.E.N.A. Laboratory at Pavia University (Laboratorio Energia Nucleare Applicata) TRIGA Mark II pool research reactor.
Department of Tool and Materials Engineering Investigation of hot deformation characteristics of AISI 4340 steel using processing map.
Crystal Linkletter and Derek Bingham Department of Statistics and Actuarial Science Simon Fraser University Acknowledgements This research was initiated.
SYSTEMS AND ENGINEERING TECHNOLOGY Sukhbinder Singh, Frazer-Nash Consultancy Development of a Finite Element Visualisation Tool for Post-Processing Graphite.
Materials Process Design and Control Laboratory Finite Element Modeling of the Deformation of 3D Polycrystals Including the Effect of Grain Size Wei Li.
17 May 2007RSS Kent Local Group1 Quantifying uncertainty in the UK carbon flux Tony O’Hagan CTCD, Sheffield.
Center for Radiative Shock Hydrodynamics Fall 2011 Review Assessment of predictive capability Derek Bingham 1.
An Adaptive-Stochastic Boussinesq Solver With Safety Critical Applications In Nuclear Reactor Engineering Andrew Hagues PhD Student – KNOO Work Package.
Preparing for the Hydrogen Economy by Using the Existing Natural Gas System as a Catalyst // Project Contract No.: SES6/CT/2004/ NATURALHY is an.
Sarah Maddox Under Hamish Gordon, Jasper Kirkby University of Michigan CERN REU Design of Experiments for the 2015 CLOUD Run.
Stress constrained optimization using X-FEM and Level Set Description
Dimensional Change of Isotropic Graphite under Heavy Ion-Irradiation Sosuke Kondo Makoto Nonaka Tatsuya Hinoki Kyoto University SEP15-18, 2013 INGSM-14.
SP2Support WP 2.1Track bed quality assessment Task Numerical modelling of poor quality sites First phase report on the modelling of poor.
Examples of Current Research in “State Awareness” for Digital Models: ICME and NDE Links to Structural Analysis Michael Enright Craig McClung Southwest.
Probabilistic Design Systems (PDS) Chapter Seven.
An agency of the Health & Safety Executive Enabling a better working world An agency of the Health & Safety Executive Enabling a better working world Nick.
Conference on Quality in Space & Defense Industries CQSDI ‘08 Probabilistic Technology Panel: What Is Probabilistic Technology? Mohammad Khalessi, Ph.D.
Reducing the risk of volcanic ash to aviation Natalie Harvey, Helen Dacre (Reading) Helen Webster, David Thomson, Mike Cooke (Met Office) Nathan Huntley.
1 Defense Programs Predictive Science and Program Credibility: “Beyond M over U” July 2008 Njema Frazier, PhD Acting Deputy Director, Office of Advanced.
1 Tom Edgar’s Contribution to Model Reduction as an introduction to Global Sensitivity Analysis Procedure Accounting for Effect of Available Experimental.
School of Mechanical and Nuclear Engineering North-West University
Sources of Radiation Research Reactors
Imaging in the Nuclear Sector Intelligent Imaging Programme Chancellor’s Hall, University of London 6th November 2013 Gary Bolton.
Introduction to emulators Tony O’Hagan University of Sheffield.
The stochastic finite element method and its possible use in thermo- mechanical drift calculations Lee Margetts, David Arregui-Mena And Paul M. Mummery.
8 Sept 2006, DEMA2006Slide 1 An Introduction to Computer Experiments and their Design Problems Tony O’Hagan University of Sheffield.
Sarah Maddox Under Hamish Gordon, Jasper Kirkby University of Michigan CERN REU Design of Experiments for the 2015 CLOUD Run.
A Primer on Running Deterministic Experiments
Panel Discussion: Discussion on Trends in Multi-Physics Simulation
Hua Liu, Zeqian Li (Student) Lin Yin (Visiting Faculty Advisor)
Finite Element Method in Geotechnical Engineering
ACCURACY IN PERCENTILES
On calibration of micro-crack model of thermally induced cracks through inverse analysis Dr Vladimir Buljak University of Belgrade, Faculty of Mechanical.
Beam Dump outline work plan (UK perspective)
Variable Selection for Gaussian Process Models in Computer Experiments
Mohammad Khalessi, Ph.D. CEO/President PredictionProbe, Inc.
SME FINITE ELEMENT METHOD
OVERVIEW OF FINITE ELEMENT METHOD
Visco-plastic self-consistent modeling of high strain rate and
Numerical Analysis of slopes
Egyptian Atomic Energy Authority (EAEA), Egypt
Presentation transcript:

INGSM-14, 16 th -18 th September 2013, Seattle, USA Development of a stress-based emulator for AGR moderator bricks M Fahad †, K McNally ‡, G Hall †, BJ Marsden †, P Mummery †, and N Warren ‡ † Nuclear Graphite Research Group, School of MACE, The University of Manchester, Manchester, England M13 9PL ‡ Statistical Modelling Team, Mathematical Sciences Unit, Health and Safety Laboratory, Harpur Hill, Buxton, England SK17 9JN

INGSM-14, 16 th -18 th September 2013, Seattle, USA Contents  Introduction  Modelling approach ongoing work  Summary

INGSM-14, 16 th -18 th September 2013, Seattle, USA Introduction  Why? AGR safety requirements  safe shutdown  continued fuel cooling AGR lifetime  structural integrity of graphite core  number and behaviour of cracked graphite components assessments and predictions of graphite and core behaviour uncertainty in predictions  internal stresses require understanding of –dimensional changes –irradiation creep (a.k.a. stress-dependent dimensional change)

INGSM-14, 16 th -18 th September 2013, Seattle, USA Introduction  Irradiation creep data many data on inert behaviour  limited for Gilsocarbon no data on combined behaviour  fast neutron irradiation + radiolytic oxidation some pre-oxidised data  new MTR programme (ACCENT) empirical relationships  informed behaviour Gilsocarbon

INGSM-14, 16 th -18 th September 2013, Seattle, USA Introduction  Inspection data graphite moderator brick channel bore measurement/inspection unit magnified deformation of a graphite moderator brick height bore diameter N

INGSM-14, 16 th -18 th September 2013, Seattle, USA Introduction  Inspection data

INGSM-14, 16 th -18 th September 2013, Seattle, USA Introduction  Emulator approach presented at INGSM-11 & INGSM-12 applied successfully for dimensional change behaviour  inspection data  constitutive equations calibrated dimensional changes  inert similar to baseline  reduced effect of oxidation

INGSM-14, 16 th -18 th September 2013, Seattle, USA Modelling approach Calibrated curves Metric Design matrix Calibration data EmulatorCalibrated parameters Simulator

INGSM-14, 16 th -18 th September 2013, Seattle, USA Modelling approach Calibrated curves Metric Design matrix Calibration data EmulatorCalibrated parameters Simulator

INGSM-14, 16 th -18 th September 2013, Seattle, USA Simulator  Representative model of physical process(es)  Finite element model of AGR brick finite element mesh loadings & boundary conditions constitutive relationships  irradiation creep –UK –EDF Energy –...  Many parameter inputs uncertainties & unknowns effect of oxidation on irradiation creep FE mesh of an AGR brick fluence temperature weight loss

INGSM-14, 16 th -18 th September 2013, Seattle, USA Modelling approach Calibrated curves Metric Design matrix Calibration data EmulatorCalibrated parameters Simulator

INGSM-14, 16 th -18 th September 2013, Seattle, USA Modelling approach Calibrated curves Metric Design matrix Calibration data EmulatorCalibrated parameters Simulator

INGSM-14, 16 th -18 th September 2013, Seattle, USA Metric  Measurement preferably available in simulator & calibration data sensitive to parameter(s) under investigation  insensitive to others  Two possibilities

INGSM-14, 16 th -18 th September 2013, Seattle, USA Metric  Stress not in calibration data compare against strength data and cracking observations

INGSM-14, 16 th -18 th September 2013, Seattle, USA Metric  Ovality

INGSM-14, 16 th -18 th September 2013, Seattle, USA Modelling approach Calibrated curves Metric Design matrix Calibration data EmulatorCalibrated parameters Simulator

INGSM-14, 16 th -18 th September 2013, Seattle, USA Modelling approach Calibrated curves Metric Design matrix Calibration data EmulatorCalibrated parameters Simulator

INGSM-14, 16 th -18 th September 2013, Seattle, USA Design matrix  Experimental design  Variation in parameter inputs adequately cover parameter space encompass parameter limits  Maximin Latin Hypercube sampling  Irradiation creep e.g. 200 design points/FE models

INGSM-14, 16 th -18 th September 2013, Seattle, USA Modelling approach Calibrated curves Metric Design matrix Calibration data EmulatorCalibrated parameters Simulator

INGSM-14, 16 th -18 th September 2013, Seattle, USA Modelling approach Calibrated curves Metric Design matrix EmulatorCalibrated parameters Simulator Calibration data

INGSM-14, 16 th -18 th September 2013, Seattle, USA irradiation oxidation Calibration data

INGSM-14, 16 th -18 th September 2013, Seattle, USA Modelling approach Calibrated curves Metric Design matrix Calibration data EmulatorCalibrated parameters Simulator

INGSM-14, 16 th -18 th September 2013, Seattle, USA Modelling approach Calibrated curves Metric Design matrix EmulatorCalibrated parameters Simulator Calibration data

INGSM-14, 16 th -18 th September 2013, Seattle, USA Emulator  Statistical approximation of simulator built using runs of simulator  design matrix/points based upon Gaussian processes in a Bayesian framework  Advantages fast  computationally efficient cf. FE models easy to modify

INGSM-14, 16 th -18 th September 2013, Seattle, USA Modelling approach Calibrated curves Metric Design matrix EmulatorCalibrated parameters Simulator Calibration data

INGSM-14, 16 th -18 th September 2013, Seattle, USA Modelling approach Calibrated curves Metric Design matrix EmulatorCalibrated parameters Simulator Calibration data

INGSM-14, 16 th -18 th September 2013, Seattle, USA Modelling approach Calibrated curves Metric Design matrix EmulatorCalibrated parameters Simulator Calibration data

INGSM-14, 16 th -18 th September 2013, Seattle, USA Calibrated curves Gilsocarbon

INGSM-14, 16 th -18 th September 2013, Seattle, USA Summary  Bayesian emulator FE model of AGR brick  Reverse engineer irradiation creep behaviour inspection data constitutive equations  Initial procedure outlined  Next stage run design points calibrate and compare re-iterate

INGSM-14, 16 th -18 th September 2013, Seattle, USA Acknowledgement The authors wish to thank the Office for Nuclear Regulation (Health & Safety Executive) for sponsoring this work. Disclaimer Any views or opinions presented are those of the authors and do not necessarily represent those of the sponsor.

INGSM-14, 16 th -18 th September 2013, Seattle, USA Development of a stress-based emulator for AGR moderator bricks M Fahad †, K McNally, G Hall, BJ Marsden, P Mummery, and N Warren † Nuclear Graphite Research Group, School of MACE, The University of Manchester, Manchester, England M13 9PL