19th International QUENCH Workshop

Slides:



Advertisements
Similar presentations
Finite element method Among the up-to-date methods of stress state analysis, the finite element method (abbreviated as FEM below, or often as FEA for analyses.
Advertisements

Thermal Behavior of Materials
Thermal Behavior of Materials
Improvements on FRAPCON3 and FRAPTRAN Mechanical Modelling Arttu Knuutila, Seppo Kelppe SAFIR-PUOLIVÄLISEMINAARI
Modeling of Neo-Hookean Materials using FEM
Mechanics. CE 336 Loadings 3 Basic Types of Loadings Static Dynamic Environmental.
INRNE-BAS MELCOR Pre -Test Calculation of Boil-off test at Quench facility 11th International QUENCH Workshop Forschungszentrum Karlsruhe (FZK), October.
11th International QUENCH Workshop, October 25-27, 2005, Forschungszentrum Karlsruhe, Germany 1 Evaluation of the Oxygen-Induced Zircaloy Embrittlement.
Residual Stress Characterization In Zirconium Oxides Using Synchrotron XRD Manchester Materials Science Centre, The University of Manchester, Grosvenor.
TensiNet Symposium SOFIA 2010 – Tensile Architecture: Connecting Past and Future September 2010, Sofia, Bulgaria Biaxial testing of architectural.
ME 450 Group Adrian Conrad Chris Cook Thomas Hylton Nathan Wagers High Pressure Water Fixture Conceptual Design Analysis December 10, 2007.
1 THE ACCURACY OF FEA. 2 REALITY MATHEMATICAL MODEL FEA MODEL RESULTS Discretization error Modeling error Solution error Discretization error is controlled.
UTILIZATION OF THE FRAPCON CODE IN BRAZIL FOR REGULATORIES MATTERS Brazilian Nuclear Energy CommisionBrazilian Nuclear Energy Commision Auro Pontedeiro.
MASTERS PROJECT FALL 2014 DAN FLAVIN 29 SEPTEMBER Springfield Rifle Bolt Analysis.
1 Technical Basis for Revising 50.46(b) ECCS Acceptance Criteria Regulatory Information Conference March 12, 2009 Ralph Meyer Division of Systems Analysis.
Copyright 2001, J.E. Akin. All rights reserved. CAD and Finite Element Analysis Most ME CAD applications require a FEA in one or more areas: –Stress Analysis.
Influence of Overload Induced Residual Stress Field on Fatigue Crack Growth in Aluminum Alloy Jinhee Park (M.S. Candidate) Date of joining Masters’ program.
Identified Company (CompositeX) to manufacture Custom Composite Pressure Vessel ● Working pressure 1000psi ● Holds 8 kg Nitrous Oxide ● 700 cubic inch.
EBB 220/3 PRINCIPLE OF VISCO-ELASTICITY
VG.1 SCWR Fuel Rod Design Requirements Design Limits Input for Performance Evaluations H. Garkisch, Westinghouse Electric Co.
4.5 FORCE METHOD OF ANALYSIS FOR AXIALLY LOADED MEMBERS
Thermal Strains and Element of the Theory of Plasticity
Structure-phase investigation and mechanical properties of Zr-1%Nb alloy claddings after LOCA tests on PARAMETR facility under 1400 °C FSUE SRI SIA «LUCH»
How detailed should a model be? Pierre Hoogenboom Delft University of Technology.
Fuel Behavior in Long-term Management of Spent Light-Water Reactor Fuel International Conference on Management of Spent Fuel from Nuclear Power Reactors.
Static & dynamic stresses from beam heating in targets & windows T. Davenne High Power Targets Group Rutherford Appleton Laboratory Science and Technology.
IRSN Views on the R & D Needs and Strategy Towards a Revision of LOCA Acceptance Criteria in France Michel SCHWARZ, Claude GRANDJEAN, François BARRE,
ZTF Cryostat Finite Element Analysis Andrew Lambert ZTF Technical Meeting 1.
An Industry Technical Position On LOCA Rulemaking 21 st Regulatory Information Conference Rockville, MD March 12, 2009 Ken Yueh Electric Power Research.
Lead Technology Task 6.2 Materials for mechanical pump for HLM reactors M. Tarantino, I. Di Piazza, P. Gaggini Work Package Meeting Karlsruhe, November.
U.S. DOT ANALYSIS OF COMPOSITE HYDROGEN STORAGE CYLINDERS UNDER TRANSIENT THERMAL LOADS J. Hu, S. Sundararaman and K. Chandrashekhara Department of Mechanical.
KIT – University of the State of Baden-Württemberg and National Large-scale Research Center of the Helmholtz Association Institute for Nuclear and Energy.
BEHAVIOUR OF MATERIALS
Andrew Wasylyk UNTF 2011 Andrew Wasylyk UNTF 2011.
1 Thermo-Mechanical Analysis of ISIS TS2 Spallation Target Dan Wilcox High Power Targets Group, Rutherford Appleton Laboratory 5th High Power Targetry.
Stress and Strain – Axial Loading
Mechanical Design of Process Equipment FUNDAMENTAL PRINCIPLES AND EQUATIONS Principal stresses Theories of failure
Workshop at Indian Institute of Science 9-13 August, 2010 BangaloreIndia Fire Safety Engineering & Structures in Fire Organisers: CS Manohar and Ananth.
Results of Linear Stress Analyses for Modular Coils and Coil structure For 2T High Beta Currents at 0 Seconds and Initial Coil Shrinkage of in/in.
1 Impact of Revised 10 CFR 50.46(b) ECCS Acceptance Criteria 2009 Regulatory Information Conference Rockville, MD March 12, 2009 Mitch Nissley Westinghouse.
ERMSAR 2012, Cologne March 21 – 23, 2012 Pretest Calculations of QUENCH-DEBRIS-0 Test Using SOCRAT/V3 Code V ASILIEV A.D. N UCLEAR S AFETY I NSTITUTE OF.
MODULE 08 MULTIDEGREE OF FREEDOM SYSTEMS. 2 Structure vibrating in a given mode can be considered as the Single Degree of Freedom (SDOF) system. Structure.
Results of First Stage of VVER Rod Simulator Quench Tests 11th International QUENCH Workshop Forschungszentrum Karlsruhe October 25-27, 2005 Presented.
Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft FZK, H & HQWS11, KA, Analysis and Comparison of Experimental Data of QUENCH-07.
Model: Thermally Induced Creep. Introduction This model computes the stress history over a long time for a material that exhibits creep behavior. The.
CAD and Finite Element Analysis Most ME CAD applications require a FEA in one or more areas: –Stress Analysis –Thermal Analysis –Structural Dynamics –Computational.
Review of Cavity Load Cases and relevant analysis L. Dassa and C. Zanoni feat. N. Kuder 08/02/2016.
Gravity load on SAS – comparison between real and mock-up April 13 th, 2016.
Date of download: 6/22/2016 Copyright © ASME. All rights reserved. From: The Importance of Intrinsic Damage Properties to Bone Fragility: A Finite Element.
TS Cool Down Studies TSu Unit Coils (24-25) N. Dhanaraj and E. Voirin Tuesday, 10 March 2015 Reference: Docdb No:
PROPERTIES OF MATERIALS ENF 150 Chapter 10: Properties of Materials.
The Thick Walled Cylinder
Characteristics of fuel rod behaviour during LOCA
Stress and Strain – Axial Loading
The Thick Walled Cylinder
-simple state of stress
CAD and Finite Element Analysis
Static & dynamic stresses from beam heating in targets & windows
Sandrine BOUTIN – Stéphanie GRAFF – Aude TAISNE – Olivier DUBOIS
FUNDAMENTALS OF METAL FORMING
Mechanics of Materials Lab
DEPARTMENT OF MECHANICAL AND MANUFACTURING ENGINEERING
326MAE (Stress and Dynamic Analysis) 340MAE (Extended Stress and Dynamic Analysis)
Adaptation of FRAPTRAN 2. 0 to VVER Fuel FRAP
IRSN work and perspectives
Fatigue to Failure: FEA Predictions of Limit Conditions for Axial Fatigue Loading of Generic Coronary Stent Designs Part 2: Geometry 1 with EP correction.
Design Validation of ITER XRCS Survey Spectrometer with Nuclear Code RCC-MR (IAEA CN-258/FIP/P1-36) Summary: The paper describes the results obtained from.
Overview of LOCA tests performed at KIT during last 30 years
First results of the bundle test QUENCH-L2 with M5® claddings
«ROSATOM» State Atomic Energy Corporation
Presentation transcript:

19th International QUENCH Workshop Relation between the newly derived ECR criterion and the QUENCH LOCA test results H.G. Sonnenburg, GRS 19th International QUENCH Workshop Karlsruhe Institute of Technology Campus North, H.-von-Helmholtz-Platz 1, 76344 Egg.-Leopoldshafen November 19-21, 2013

Overview Phenomena During LOCA Transient Development of a New ECR-Criterion KIT QUENCH LOCA Tests for Safety Assessment

Phenomena during LOCA Time Temperature at burst ~800°C Oxidation secondary Hydriding Temperature Thermal shock Quenching fluid shakes the broken fuel rod   135°C Depletion phenomenon seen in HALDEN and STUDSVIK Depletion phenomenon seen in STUDSVIK by shaking the rod Depletion of ~ 0.1 m fuel if: a) cladding burst b) high burn-up Depletion of ~ 1.5 m fuel if: a) cladding is already burst b) no residual ductility left c) high burn-up

Present Regulatory Limit for LOCA (international) Maintain coolable geometry Keep fuel inside cladding Prevent breaking cladding Maintain residual ductility in cladding Limit oxidation (Limit hydriding - not considered yet) Oxidation limits Keep equivalent cladding reacted below 17%  ECR < 17% Keep oxidation temperature below 1200°C  PCT < 1200°C Keep hydriding below ???  ECR=ECR(H)

Need for new ECR Criterion Proposal from U.S.NRC derived from Ring Compression Tests (offset strain >2%) Proposed criterion relies on a few tests which fall close to zero ductility 17% ECR Secondary Hydriding during LOCA ?

Alternative Approach to Derive the ECR Criterion

sBurst(e) Finite Element Method ECR  total O-up-take Leistikov  ZrO-, ZrO2-layers  O in prior-b-layer MATPRO  E(O), n(O), K(O)  sYield(O) Finite Element (ADINA): localization of maximum equivalent stress  sBurst(e) Load (N) 700 600 ADINA sBurst(e) 500 400 Ring Compression Test (ANL) 300 200 100 1 2 3 4 Displacement (mm)

Burst Stresses from 65 RCTs (room temperature) out of 102 RCTs

Stress Ratio R = Function (Material, TRCT, ECR, ppm H) Zero-ductility: R = 1 ECR = 17%

Linear Regression for Stress Ratio R 𝑅= 𝜎 𝑏𝑢𝑟𝑠𝑡 𝜎 𝑦𝑖𝑒𝑙𝑑 = 𝑎 0 + 𝑎 𝐸𝐶𝑅 +𝑎 𝐻,𝐸𝐶𝑅 𝑐 𝐻 𝐸𝐶𝑅+ 𝑎 𝑇 𝑇 +𝑎 𝐻 𝑐 𝐻 based on 102 RCTs Estimate Std. Error p-value 𝑎 0 1.62 3.5 . 10-2 < 2 . 10-16 𝑎 𝑇 ( 1 °𝐶 ) 1.8 . 10-3 3.6 . 10-4 1.6 . 10-6 𝑎 𝐸𝐶𝑅 ( 1 % 𝐸𝐶𝑅 ) (Zry-4, ZIRLO) -4.2 . 10-2 3.0 . 10-3 𝑎 𝐸𝐶𝑅 ( 1 % 𝐸𝐶𝑅 ) (M5) -3.7 . 10-2 2.8 . 10-3 4.1 . 10-9 𝑎 𝐸𝐶𝑅 ( 1 % 𝐸𝐶𝑅 ) (Zry-4 HBR) -6.5 . 10-2 4.2 . 10-3 𝑎 𝐻 ( 1 𝑝𝑝𝑚 𝐻 ) -1.05 . 10-4 1.7 . 10-5 1.0 . 10-8 𝑎 𝐻,𝐸𝐶𝑅 ( 1 % 𝐸𝐶𝑅 𝑝𝑝𝑚 𝐻 ) -1.08 . 10-4

Zero-Ductility 𝐸𝐶𝑅 𝑅=1 𝐸𝐶𝑅 𝑅=1 = 1− 𝑎 0 − 𝑎 𝑇 𝑇𝑅𝐶𝑇 −𝑎 𝐻 𝑐 𝐻 𝑎 𝐸𝐶𝑅 +𝑎 𝐻,𝐸𝐶𝑅 𝑐 𝐻 ECR in % secondary hydriding during LOCA ? H in wppm

Conservatism of ECRR=1 ECRR=1  Burst stress at yield stress level Accuracy of burst stress is ±20% Yield stress ranges from 500 MPa to 900 MPa (MATPRO) Thermo-elasticity: Estimated stress level for thermal shock (Quenching DT 800°C  135°C) 𝜎 ΘΘ = 𝛼 𝐸 Δ𝑇 2 (1−𝜈) 1 ln⁡ 𝑑 𝑜𝑢𝑡𝑒𝑟 𝑑 𝑖𝑛𝑛𝑒𝑟 − 2 𝑑 𝑜𝑢𝑡𝑒𝑟 𝑑 𝑖𝑛𝑛𝑒𝑟 2 −1 ≈250 𝑀𝑃𝑎 ECRR=1 implies huge conservatism against breaking of fuel rods

Prototypic Fuel Rod Bundle Tests for Safety Assessment obsolete 17% ECR limit Oxidation/Hydriding inacceptable ECR (%) ECRR<1 OCZL#19 ECRR=1 Expected Prototypic Bundle Tests at KIT ECRR>1 Oxidation/Hydriding acceptable

Conclusion Fuel rod behaviour under LOCA can be assessed including hydriding / oxidation near burst opening even at high H content New criterion: ECRR=1 prevents KIT bundle tests (QUENCH LOCA test) provide combination of hydriding and oxidation near burst opening Safety assessment  Comparison between H / ECR and ECRR=1