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  • Slide 1

    ASME B&PV III, Div. 5 Section H

    Code on Nuclear Graphite Core

    Components

    Technical Meeting on High-Temperature Qualification of

    High-Temperature Gas Cooled Reactor Materials

    IAEA, Vienna

    Jan 10-13, 2014

    Tim Burchell, Mark Mitchell and Mike Davies, BPC-III Working

    Group Graphite & Composite Design

  • Acknowledgements

    This work is sponsored by the

    U.S. Department of Energy, Office of Nuclear Energy, Advanced Reactor

    Technology Program, under contract DE-AC05-00OR22725 with Oak Ridge

    National Laboratory, managed by UT-Battelle, LLC

  • Slide 3

    Contents

    Here we present some information on the rules for the design and construction of graphite core components of a High Temperature Reactor.

    Contents: HTRs and their Graphite Core Components (GCC)

    Progress and structure of the code

    proposed criteria for the design of Graphite Core Components

    Introduction (GCC In Safety Case)

    Modes of failure, Stress categories and Stress Limits

    Design Margin Comparison

    Verification of methods

    New verification exercise/methodology

    Conclusion

  • Slide 4

    Graphite Core Components Prism Type

    HTR (HTTR)

  • Slide 5

    Graphite Core Components Pebble Type

    HTR (PBMR)

  • Slide 6

    Overview of the code documents

    Part HAB: General Requirements for Graphite Core Components HAB-1000 Introduction

    HAB-2000 Classification of Graphite Core Components

    HAB-3000 Responsibilities and Duties

    HAB-4000 Quality Assurance

    HAB-5000 Authorized Inspection

    HAB-7000 Reference Standards

    HAB-8000 Certificates and Data reports

    Part HHA: Technical Requirements for Design and Construction of Non Metallic Core Support Structures (Graphite GB- HHA 1000 Introduction

    HHA -2000 Materials

    HHA -3000 Design

    HHA -4000 Machining and installation

    HHA -5000 Examination

    HHA -6000 Testing

    HHA -8000 Nameplates, Stamping and Reporting

    Appendix HHA-I Graphite Material Specifications

    Appendix HHA-II Requirements for creation of a material datasheet

    Appendix HHA-III Requirements for Generation of Design Data for Graphite Grades

    Appendix HHA-IV contamination control requirements for graphite core components and core assemblies

    Appendix HHA-A Graphite as a structural material

  • Slide 7

    Major Design Code Issues

    Selected design methodology Probabilistic:

    Design margin related to material uncertainty.

    Defined in Appendix 3 Material Qualification, not prescribed in the code

    Core Component vs. assembly design, catering for damage tolerance assessment.

    Designer selection and classification of parts for structural reliability.

    Design for effect of environmental effects over operating life (Irradiation, Oxidation)

  • Graphite Data and ASME Code Development

    8

    Application of the AGC Data to the ASME B&PV Code, Division III, Sect 5:HTRs, Rules for

    Construction of Nuclear Facility Components

    HHA-2220 IRRADIATED MATERIALS PROPERTIES

    (a) The Materials Data Sheet shall include the properties specified in Mandatory Appendix

    HHA-II. Fast neutron irradiation effects on the following properties shall be required for

    compliance with this Subpart:

    1) Dimensional change

    2) Creep coefficient

    3) Coefficient of thermal expansion

    4) Strength

    5) Thermal conductivity

    6) Elastic modulus

    (b) The magnitude of the material property change depends on the damage dose and

    irradiation temperature. The damage dose and temperature range for the measurements shall

    cover the qualification envelope range of HHA-2131(a), or as required in the application of the

    graphite grade in the Graphite Core Assembly

  • Graphite Data and ASME Code Development

    9

    HHA-3142 Irradiation Effects

    Neutron Fast Fluence

    Limit

    (DPA)

    Condition Design Analysis Requirement

    0.001 Irradiated Effect on thermal

    conductivity shall be

    considered (thermal

    stress and stress

    gradients)

    >0.25 Irradiated Full viscoelastic

    analysis.

    Full effects of neutron

    irradiation (HHA-2220)

  • Graphite Data and ASME Code Development

    10

    HHA 3142.3 Internal Stresses Due to Irradiation

    The internal stresses in a graphite core component [that exceed the dose limits described in

    HHA-3142.1(c)] shall be calculated. This calculation shall be completed by viscoelastic

    modeling of the material behavior.

    (a) Irradiation induced property changes creep and changes in properties (elastic modulus,

    CTE, thermal conductivity) shall be accounted for in this analysis. The interaction between

    irradiation creep and the CTE shall be included in this assessment.

    (b) The analysis shall account for stress concentrations resulting from Graphite Core

    Component geometry.

    (c) The stress analysis shall account for superposition of stresses resulting from all of the

    loads that a Graphite Core Component is exposed to simultaneously.

    HHA-3142.4 Graphite Cohesive Life Limit

    A temperature-dependent cohesive life limit is to be defined for the graphite grade used for

    the Graphite Core Components. Material that exceed this life limit is considered to provide

    no contribution to the structural performance (stiffness and strength) of the Graphite Core

    Component. This fluence limit shall be set to the fluence at which the material experiences a

    +10% linear dimensional change in the with-grain direction. For full assessment (HHA-

    3230) this material shall not be included in the volume of the Graphite Core Component

    assessed.

  • Graphite Data and ASME Code Development

    11

    MANDATORY APPENDIX HHA-III

    REQUIREMENTS FOR GENERATION OF DESIGN DATA FOR GRAPHITE GRADES

    HHA-III-3300 IRRADIATED GRAPHITE

    For irradiated graphite [HHA-3132.1(b) and (c)] the following properties shall be determined:

    (a) thermal conductivity temperature dependent

    (b) dimensional change [HHA-3132.1(c) only]

    (c) creep coefficients [HHA-3132.1(c) only]

    (d) CTE temperature dependent [HHA-3132.1(c) only]

    (e) strength [HHA-3132.1(c) only]

    (f) elastic modulus [HHA-3132.1(c) only]

    Test data shall represent and envelope the irradiation conditions in service, i.e., they shall

    mimic reactor neutron fluence and temperature ranges. Data shall be reported in accordance

    with ASTM C625.

    FORM MDS-1 MATERIALS DATA SHEET (SI UNITS)

    This form provides a template for the required graphite properties.

    Hope to accumulate data by grade/property (or algorithm) and incorporate as ASME Code

    cases

  • Slide 12

    HHA-3000: TABLE OF CONTENTS HHA-3100 GENERAL DESIGN

    HHA-3110 Graphite core components

    HHA-3120 Loading Criteria (Design & Service loadings)

    HHA-3130 Nomenclature

    HHA-3140 SPECIAL CONSIDERATIONS HHA-3141 Oxidation

    HHA-3142 Irradiation Effects

    HHA-3143 Abrasion and Erosion

    HHA 3144 Fatigue (on ballett)

    HHA-3145 Compressive Load

    HHA-3200 DESIGN BY ANALYSIS HHA-3210 DESIGN CRITERIA

    HHA-3211 Requirements for acceptability

    HHA-3212 General Design Requirements for Graphite Core Components

    HHA-3213 Basis for Determining Stresses

    HHA3214 Terms Relating to Stress Analysis

    HHA-3215 Stress Analysis

    HHA-3220 Stress Limits for GCC Simplified Assessment (Stress intensity based limits. These are related to the failure probability limits in the next section.)

    HHA-3230 Probability of Failure Limits for GCC Full Assessment (Failure probability limits and how to assess to them.)

    HHA-3240 Experimental limits - Design by test (For both static and fatigue strength.)

    HHA-3300 REQUIREMENTS FOR DESIGN OF GRAPHITE CORE ASSEMBLY

  • Slide 13

    Design Criteria for GCC

    Brief overview of the criteria for the design of the

    GCC. Supporting Article HHA-3000.

    Key concepts: Role of GCC in A HTR Safety Case.

    Modes of Failure addressed

    Determination of Limits

    Material Reliability Curve

    Probabilistic Assessment Simplified Assessment

    Probabilistic Method Full Assessment

    Comparison of Margins

    Verification (current & planned)

  • Slide 14

    GCC In safety Case Graphite is quasi-brittle.

    Graphite Strength shows a high variability.

    It is not necessarily possible to ensure against cracking of graphite components.

    A Graphite Core Assembly design shall ensure that the Failure (cracking) of a GCC does not result in loss of functional integrity of the Graphite Core Assembly.

    As opposed to a pressure vessel, damage tolerance in GCA in ensured by limiting the consequence of failure of a single GCC, thus damage tolerance is ensured by assemblies of many components where no single component is critical to the functional integrity of the component.

  • Slide 15

    Modes of failure

    The identified modes of failure for graphite are:

    Brittle fracture

    Based on small numbers of parts cracking. Related to loss of function. Material dependent.

    Fatigue

    Buckling (Elastic Instability)

    Environmental effects.

    Oxidation

    Water vapour

    Irra