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G 74 MA 6 01-05-28 W0.4
ITER
Structural Design Criteria
for ITER
General Section
(SDC-G)
ITER
G 74 MA 6 01-05-28 W0.4
Structural Design Criteria for ITER, General Section
Table of Contents
G 1. Introduction ...............................................................................................................3
G 2. Basis for general approach .........................................................................................3
G 2.1.
Scope .................................................................................................................3
G 2.2.
Code selection....................................................................................................3
G 2.3.
Design requirements and service conditions .......................................................5
G 2.4.
Criteria levels.....................................................................................................5
G 2.5.
Materials and design allowables .........................................................................6
G 3. Structural Design Code specification..........................................................................7
G 3.1.
Magnet structures...............................................................................................7
G 3.1.1.
Scope .........................................................................................................7
G 3.1.2.
Basis for criteria - SDC-MC .......................................................................7
G 3.2.
In-vessel components .........................................................................................8
G 3.2.1.
Scope .........................................................................................................8
G 3.2.2.
Basis for criteria - SDC-IC .........................................................................8
G 3.3.
Vacuum vessel and ex-vessel components..........................................................9
G 3.3.1.
Scope .........................................................................................................9
G 3.3.2.
Basis for criteria - vacuum vessel and ex-vessel components ......................9
G 3.3.2.1. VV, Cryostat and other pressure vessels .................................................9
G 3.3.2.2. Piping ...................................................................................................10
G 3.3.2.3. Piping components: valves, fittings, flanges, and bolting .....................10
G 3.3.2.4. Pumps...................................................................................................10
G 3.3.2.5. Component supports .............................................................................11
G 3.3.2.6. Expansion joints (bellows)....................................................................11
G 3.3.2.7. Other components.................................................................................11
G 3.4.
Buildings..........................................................................................................12
G 4. List of applicable criteria for each WBS (level 2).....................................................13
G 5. Stress report requirement .........................................................................................16
G 6. List of codes and standards ......................................................................................18
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G 1. Introduction
The purpose of this document is to provide the guideline for structural design criteria used for
various components of ITER.
G 2. Basis for general approach
G 2.1. Scope
This document (SDC) contains the guide to the code selection that shall be used for structural
analysis of different ITER components. The details of the analyses to be carried out are given
in the listed codes and standards.
The SDC does not contain procedures for quality assurance, non-destructive examination and
in-service inspection. These issues should be addressed in the component design documents
and in procurement specifications in accordance with codes selected.
G 2.2. Code selection
ITER structural design criteria fall into three categories based on the unique characteristics of
the components. Each category has had its own development strategy, as follows:
1.
Criteria for superconducting magnets and structures (SDC-MC1). Industry
pressure vessel based codes do not apply owing to the unique characteristics of the
structure, which include cryogenic temperatures and insulation as well as
magnetic loads. ITER-specific criteria, SDC-MC, have been developed by the
JCT and the Home Teams.
2.
Criteria for in-vessel components (SDC-IC2,). Industry codes do not apply
owing to unique materials, radiation damage to the materials leading to
embrittlement, swelling, enhanced creep, and the multi-layered, inhomogeneous
structure. ITER-specific criteria, SDC-IC, have been developed for structural
analysis of in-vessel components.
3.
Existing industrial codes are used for all other components. It was decided that
US codes and standards would be adopted because the US standards are familiar
to most participants and because they are the origin of and consistent with many
other national standards. In particular, the ASME Boiler and Pressure Vessel code
and related codes for piping, valves, and pumps are adopted as the standards for
the project.
Figure G 2.2-1 shows the diagram of Structural Design Criterion used for different ITER
components. Either existing industrial codes or SDC-IC could be applied to the components
with WBS 5.1-5.6 depending on the location of their portion (see G 3.2, G 3.3 and G 3.5).
In some cases the structure, the material behavior and/or the loading might be too
complicated to be evaluated using stress analysis alone. The provision for "design by
experiment" is an acknowledgment that some aspects of the in-vessel components, such as
1
2
G 74 MA 11, Structural Design Criteria for Magnet Components (SDC-MC)
G 74 MA 8, ITER Structural Design Criteria for In-vessel Components (SDC-IC)
Structural Design Criteria
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material interfaces and nonlinear material behaviour, may be too complex to rely on stress
analysis alone.
Structural Design Criteria for ITER
(SDC-G)
G 74 MA 6
Structural Design
Criteria for Magnet
(SDC-MC)
G 74 MA 11
Structural Design Criteria
for In-vessel Components
(SDC-IC)
G 74 MA 8
Existing Industrial
Standards
(ASME, EJMA, etc.)
1.1 - Magnet
1.6 - Blanket System
1.5 - Vacuum Vessel
1.7 - Divertor
2.4 - Cryostat
2.6 - Cooling water
2.7 - Thermal shields
3.2 - Tritium plant
and detritiation
3.4 - Cryoplant and
cryodistribution
6.2- - Buildings,
6.4 Layout, Hot Cells,
Waste Processing
and Environmental
Monitoring
6.5 - Liquid & Gas
Distribution
5.1 - Ion Cyclotron Heating & Current Drive
(ICH&CD)
5.2 - Electron Cyclotron Heating & Current Drive
(ECH & CD)
5.3 - Neutral Beam Heating & Current Drive
(NBH&CD)
5.4 - Lower Hybrid Heating & Current Drive
(LHH&CD)
5.5 - Diagnostics
5.6 - Test Blanket
Figure G 2.2-1. Schematic diagram of structural design codes application for the
ITER components analysis.
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G 2.3. Design requirements and service conditions
ITER identifies four categories of event (or conditions):
I - Operational,
II - Likely,
III - Unlikely,
IV -Extremely unlikely.
The different damage limits are specified depending on the category events and relevancy of
the component to the safety class (SIC). Categories of the damage limits are given in DRG13.
The designers shall specify the loading conditions depending on the event categories and
damage limits for each of the component. General rules for the loading specification are
given in Load Specification and Combination document (LS) 4.
G 2.4. Criteria levels
Criteria levels are aimed at preventing a specific degree of damage to the component in
question. Four distinct criteria levels are given: A, B, C, and D, with the general objectives
defined below:
Criteria Level
General objective
A
Negligible damage. All structures, systems, and
components are functional.
B
Negligible damage. All structures, systems, and
components are functional. Anticipated maintenance and
minor adjustment might be required. Same service level
as for Criteria Level A but with lower margin.
C
May be significant local distortion. May need to inspect,
call for repair or replacement of faulty components.
D
May be large general distortion and investment loss.
Repair may not be considered economic. Minimum safety
functions shall be maintained.
Service conditions or criteria levels are used in accordance with the codes identified in this
document for each component (see G 3).
3
4
G A0 GDRD 2, Design Requirements and Guidelines Level 1 (DRG1)
G A0 MA 1, Load Specification and Combination.
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The analysis and terminology of different codes are not necessary identical (for example,
ASME5 specifies Service Limits A, B, C and D). It is recommended to use terminology and
analysis as prescribe in the code used for each component in accordance with G 3.
G 2.5. Materials and design allowables
The material properties used in the analysis (particularly allowable stresses) shall be defined
by the code used for each component.
If material grades or properties differ from those given in the code, justification documents
shall be provided.
5
ASME Boiler and Pressure Vessel Code, 1995 Edition, Section III, Subsection NCA2142.4, The American
Society of Mechanical Engineers, New York, 1995.
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G 3. Structural Design Code specification
G 3.1. Magnet structures
G 3.1.1.
Scope
The ITER-specific Structural Design Criteria for Magnets Components (SDC-MC)1, are
applicable to the superconducting coils and structures with WBS 1.1. These are conductor,
insulation, coil cases and associated bracing structures, gravity supports, superconducting
busbars supplying the coils and cryogenic pipelines. The criteria are also applicable to the
keys and bolts used for the coil and support structures.
G 3.1.2.
Basis for criteria - SDC-MC
The main purpose of the ITER magnet structural criteria is to establish a design code and
component assessment methodology relevant to components operating in the range 4-77K
and extended to room temperature under abnormal operating conditions. Existing codes
generally exclude this low temperature range but the methodologies in these codes are in
many cases applicable.
The structures that this document refers to are magnets and their support structures. These
will have a different stress system compared to plants consisting of pressure vessels, pipes
and their supports, and use different types of materials. However various design methods
reviewed for the so-called 'defect free' codes [ASME pressure vessel code 7, RCC-MR 6] as
well as those dealing explicitly with defects in structures [R6, BS7910, API579] have been
found in most cases to be compatible for use in the cryogenic temperature range when the
relevant material properties are used. There are certain conditions with regards to the magnet
components that this document will address. Operating largely without in-service inspection,
the questions of safety factors, the operating loads, residual stresses, non-destructive
examination sensitivity and reliability, and accuracy of material data relevant to the fracture
and fatigue prediction procedures, become more significant at the design stage for the
magnets than for conventional high temperature components.
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G 3.2. In-vessel components
G 3.2.1.
Scope
The ITER Structural Design Criteria for In-vessel Components (SDC-IC)2 is applicable to the
following WBS elements:
WBS
1.6
1.7
Title
Blanket System
Divertor
In addition, the SDC-IC is applicable to in-vessel portions of other WBS elements. These
WBS elements include the following table:
WBS
1.8
5.1
5.2
5.3
5.4
5.5
5.6
G 3.2.2.
Title
Fuelling
Ion Cyclotron Heating & Current Drive (ICH & CD) System
Electron Cyclotron Heating & Current Drive (ECH & CD) System
Neutral Beam Heating & Current Drive (NBH & CD) System
Lower Hybrid Heating & Current Drive (LHH & CD) System
Diagnostics
Test Blankets
Basis for criteria - SDC-IC
SDC-IC development was undertaken as a collaboration among the four Home Teams of
Europe, Japan, the Russian Federation, and the United States. The SDC-IC are based on the
RCC-MR code6, as a convenient starting point, and extensive modifications have been
provided to include unique structure of ITER components, useful features of other codes (in
particular ASME), and national requirements to address the unique features of these
components.
6
"Design and Construction Rules for Mechanical Components of FBR Nuclear Islands (RCC-MR), June 1985
Edition", Paris".
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G 3.3. Vacuum vessel and ex-vessel components
G 3.3.1.
Scope
The codes and standards listed in this section apply generally to ITER ex-vessel components
other than the magnets and the buildings. These components are within the following
elements:
WBS
1.5
2.4
2.6
2.7
3.2
3.4
5.1
5.2
5.3
5.4
5.5
5.6
6.5
Title
Vacuum Vessel (VV)
Cryostat
Cooling water
Thermal shields
Tritium plant and detritiation
Cryoplant and cryodistribution
Ion Cyclotron Heating & Current Drive (ICH & CD) System
Electron Cyclotron Heating & Current Drive (ECH & CD) System
Neutral Beam Heating & Current Drive (NBH & CD) System
Lower Hybrid Heating & Current Drive (LHH & CD) System
Diagnostics
Test Blankets
Liquid & Gas Distribution
These include parts of components located in ex-vessel areas. (Some components are located
inside the VV, for example, diagnostic components. SDC-IC should be applied for these parts
located inside of VV.)
Specific components are discussed below.
G 3.3.2.
Basis for criteria - vacuum vessel and ex-vessel components
G 3.3.2.1.
VV, Cryostat and other pressure vessels
ASME Section VIII Division 2 7 shall be used for the vacuum vessel, cryostat and ex-vessel
component design for loading conditions of the Category I and II (Design A condition, see
ASME-VIII, Table AD-150.1).
The ASME Section VIII identifies loading conditions as Design A, B, C or D. The Design A
rules (ASME VIII div.2) shall be used for the ITER Category I and II events to maintain the
DRG1 requirement on withstanding Category I and II loads without damage that requires
inspection or repair. Design categories B, C and D of ASME VIII are not used for ITER.
For the VV and cryostat, ITER identifies exceptional loading conditions (Categories III and
IV, Unlikely and Extremely Unlikely Loadings) and permits local deformation providing the
structural integrity and safety functions are maintained. The analysis of these unlikely events,
Categories III and IV, is not explicitly addressed in ASME Section VIII. For these
exceptional loading conditions (Cat. III and IV), the allowable stresses from ASME III Level
7
ASME Boiler and Pressure Vessel Code, 1995 Edition, Section VIII Division 2, Alternative rules. (Rules for
Construction of Pressure Vessels), The American Society of Mechanical Engineers, New York, 1995.
Structural Design Criteria
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G 74 MA 6 01-05-28 W0.4
C (Cat. III) and Level D (Cat. IV) 8 shall be used to demonstrate that the safety function is
maintained.
Application of these design rules should be restricted only to components inside and
including the cryostat, not to all systems. Outside of the cryostat ASME Section VIII
Division 2 shall be applied without exception.
However, ASME Section VIII Division 2 does not contain buckling limits in the rules for
design by analysis, and there is no explicit rule for vessels loaded by external pressure. The
buckling rules of ASME Section III-NH shall be used for all components under external
pressure or compressive load.
G 3.3.2.2.
Piping
The selected piping code, ASME B31.39 is a section of the ASME Code for Pressure Piping,
B31.
The organization and provisions of this code are similar to ASME Section VIII, to which it is
a companion. Service Category M is applicable to radioactive fluids, e.g., tritiated water, etc.
This code also allows operation at cryogenic temperature.
G 3.3.2.3.
Piping components: valves, fittings, flanges, and bolting
ASME B31.39 contains a Chapter IV, Standards for Piping Components, in which Table
326.1 lists standards for various components, including valves, fittings, flanges, and bolting.
For the components listed in that table, the dimensional standards apply, and the pressure and
temperature ratings of the components are accepted for pressure design in accordance with
B31.3 paragraph 304.7.1. Unlisted components may also be used provided that they satisfy
conditions in B31.3 paragraph 304.7.2.
ASME B16.3410 is the generic standard for flanged and welded valves. It is accepted by its
inclusion in B31.3 Table 326.1. If piping components not covered by B16.34 are needed,
additional standards can be selected, from Table 326.1.
G 3.3.2.4.
Pumps
ASME B31.39 excludes pumps from its scope. Two ANSI standards applicable to ITER and
which are consistent with B31.3 are ASME B73.1M11 and ASME B73.2M12.
ANSI standards are selected as the preferred path because of lower cost and consistency with
other industry-standard codes. However, if specialty pumps are needed for which there are no
8
ASME Boiler and Pressure Vessel Code, 1995 Edition, Section III Division 1 (Rules for Construction of
Nuclear Power Plant Components), Subsection NC, Class 2 Components, The American Society of Mechanical
Engineers, New York, 1995.
9
"Chemical Plant and Petroleum Refinery Piping (ASME B31.3 - 1990)," The American Society of Mechanical
Engineers, New York
10
"Valves - Flanged, Threaded, and Welding End (ASME B16.34 - 1988)," The American Society of
Mechanical Engineers, New York
11
"Horizontal End Suction Centrifugal Pumps for Chemical Processes (ASME B73.1M - 1991)," The American
Society of Mechanical Engineers, New York
12
"Vertical In-Line Centrifugal Pumps for Chemical Processes (ASME B73.2M - 1991)," The American
Society of Mechanical Engineers, New York
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ANSI standards, the rules of ASME Section III-NC could be used. Other standards may be
selected and justified on a case-by-case basis.
G 3.3.2.5.
Component supports
The code for the supports is ASME Section III-NF13, which includes rules for both shell and
linear component, as well as criteria for the different loading categories.
G 3.3.2.6.
Expansion joints (bellows)
ASME B31.3 shall be used for the design analysis of bellows. In particular, Appendix X of
this standard contains the allowable stress and safety factors. The EJMA Standard can be
used for the details of the design.
G 3.3.2.7.
Other components
The industry standard codes in the same family as ASME Section VIII and ASME B31.3
may be used. Selected codes should be identified with justification of their applicability.
13
ASME Boiler and Pressure Vessel Code, 1995 Edition, Section III Division 1 (Rules for Construction of
Nuclear Power Plant Components), Subsection NF, Component Supports, The American Society of Mechanical
Engineers, New York, 1995.
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G 74 MA 6 01-05-28 W0.4
G 3.4. Buildings
The buildings (WBS 6.2-6.4) are divided into three categories. Appropriate codes given in
Table G 3.4-1 or equivalent can be used for the design analysis.
Table G G 3.4-1. Basic Structural Codes for Buildings
Building category
Construction code
reinforced concrete - general
purpose
ACI 318M-89 14
reinforced concrete - nuclear
safety related
ACI 349-90 15
Steel frame
Uniform Building Code 16
AISC steel construction criteria 17 and 18
14
Building Code Requirements for Reinforced Concrete (ACI 318M-89) (Revised 1992)," American Concrete
Institute, Detroit, 1992.
15
Code Requirements for Nuclear Safety Related Concrete Structures (ACI 349-90)," American Concrete
Institute, Detroit, 1990.
16
Uniform Building Code, 1994 Edition, International Conference of Building Officials, Whittier, California.
17
"AISC Manual of Steel Construction Ð Allowable Stress Design, Ninth Edition," American Institute of Steel
Construction, Inc., Chicago, 1989.
18
"AISC Specification for Structural Steel Buildings - Allowable Stress Design and Plastic Design, June 1,
1989, with Commentary," American Institute of Steel Construction, Inc., Chicago, 1989.
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G 4. List of applicable criteria for each WBS (level 2)
Table 4.-1 contains a cross reference between the structural design criteria for each ITER
component at WBS level 2. Structural design criteria apply only to engineered structures.
Some components include only purchased equipment, in which case "Not Applicable" (N/A)
is noted.
Table G 4.-1. List of applicable criteria for each WBS element
WBS
No.
1.1
Title
Selected Criteria
Magnet
Structural Design Criteria, Vol.2, Magnet (SDC-MC)
1.5
Vacuum Vessel
1.6
Blanket System
ASME Section VIII Div. 2
ASME Section III-NC for Cat III and IV Events
Structural Design Criteria, Vol.1, In-Vessel Components (SDC-IC)
1.7
Divertor
Structural Design Criteria, Vol.1, In-Vessel Components (SDC-IC)
2.3
No specific criteria are identified
2.4
Remote Handling (RH)
Equipment
Cryostat
2.6
Cooling Water
2.7
Thermal Shields
3.1
Vacuum Pumping &
Fueling
3.2
Tritium Plant &
Detritiation
3.4
4.1
Cryoplant and
Cryodistribution
Pulsed & Steady State
Power Supplies
Structural Design Criteria
vessel:
ASME Section VIII Div. 2
piping:
ASME B31.3
supports:
ASME Section III-NF
bellows:
ASME B31.3, Appendix X/EJMA
ASME Section III-NC for Cat III and IV Events
vessels:
ASME Section VIII Div. 2 *
piping
ASME B 31.3, Category M
pumps
ASME B73.1M / B73.2M
valves
ASME B16.34
supports
ASME Section III-NF
bellows:
ASME B31.3, Appendix X/EJMA
ASME Section III-NC for Cat III and IV Events **
ASME Section VIII Div. 2
ASME Section III-NC for Cat III and IV Events
vessels:
ASME Section VIII Div. 2
piping:
ASME B31.3
vessels:
ASME Section VIII Div. 2 *
piping
pumps
valves
supports
bellows:
vessels:
piping
pumps
valves
supports
bellows:
N/A
ASME B 31.3, Category M
ASME B73.1M / B73.2M
ASME B16.34
ASME Section III-NF
ASME B31.3, Appendix X/EJMA
ASME Section VIII Div. 2 *
ASME B 31.3, Category M
ASME B73.1M / B73.2M
ASME B16.34
ASME Section III-NF
ASME B31.3, Appendix X/EJMA
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5.1
5.2
5.3
5.4
5.5
G 74 MA 6 01-05-28 W0.4
Ion Cyclotron Heating
& Current Drive (ICH
& CD) System
Electron Cyclotron
Heating & Current
Drive (ECH & CD)
System
Neutral Beam Heating
& Current Drive (NBH
& CD) System
Lower Hybrid Heating
& Current Drive (LHH
& CD) System
Diagnostics
Irradiated items:
Structural Design Criteria, Vol.1, In-Vessel Components (SDC-IC)
Unirradiated items:
vessels:
ASME Section VIII Div. 2 *
piping:
ASME B31.3
supports:
ASME Section III-NF
bellows:
ASME B31.3, Appendix X/EJMA
ASME Section III-NC for Cat III and IV Events **
Irradiated items:
Structural Design Criteria, Vol.1, In-Vessel Components (SDC-IC)
Unirradiated items:
vessels:
ASME Section VIII Div. 2 *
piping:
ASME B31.3
supports:
ASME Section III-NF
bellows:
ASME B31.3, Appendix X/EJMA
ASME Section III-NC for Cat III and IV Events **
Irradiated items:
Structural Design Criteria, Vol.1, In-Vessel Components (SDC-IC)
Unirradiated items:
vessels:
ASME Section VIII Div. 2 *
piping:
ASME B31.3
supports:
ASME Section III-NF
bellows:
ASME B31.3, Appendix X/EJMA
ASME Section III-NC for Cat III and IV Events **
Irradiated items:
Structural Design Criteria, Vol.1, In-Vessel Components (SDC-IC)
Unirradiated items:
vessels:
ASME Section VIII Div. 2 *
piping:
ASME B31.3
supports:
ASME Section III-NF
bellows:
ASME B31.3, Appendix X/EJMA
ASME Section III-NC for Cat III and IV Events **
Irradiated items:
Structural Design Criteria, Vol.1, In-Vessel Components (SDC-IC)
Unirradiated items:
vessels:
ASME Section VIII Div. 2 *
piping:
ASME B31.3
supports:
ASME Section III-NF
bellows:
ASME B31.3, Appendix X/EJMA
ASME Section III-NC for Cat III and IV Events **
Structural Design Criteria, Vol.1, In-Vessel Components (SDC-IC)
5.6
Test Blankets
6.2
Buildings & Layout
concrete (normal):
concrete (safety related):
steel frame:
6.3
Hot cells & Waste
Processing
Radiological and
Environmental
Monitoring
Local building code
6.4
Structural Design Criteria
ACI 318
ACI 349
UBC, AISC
Local building code
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6.5
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Liquid & Gas
Distribution
vessels:
piping:
supports:
bellows:
ASME Section VIII Div. 2 *
ASME B31.3
ASME Section III-NF
ASME B31.3, Appendix X/EJMA
Notes: * Section VIII Div. 2 is selected for pressure vessels. However, it is possible
that this could be changed to Section VIII Div. 1 for certain pressure vessels if
analysis shows Div. 1 to be warranted.
** Application of these design rules should be restricted to components inside
and including the cryostat, if required.
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G 5. Stress report requirement
Calculations made to check the rules contained in the SDC shall be documented in design
calculation notes, memos and, where necessary, a summary report.
The design documents shall include a stress report for all the components designed in
accordance with the rules of the SDC. The report shall demonstrate that the criteria are
satisfied for all loadings specified in the component data file. They shall also demonstrate
that any additional design requirements contained in the component data file are met.
The typical organization of the stress report is as follows:
Introduction
The introduction defines the component concerned, its structure, its limits, the design
conditions, and the design and construction class.
Basic data
Description of the geometry of the structures, interface information (boundary
conditions), and loadings, with explanatory diagrams where possible.
Materials
The reference to the materials data shall be provided.
Specified criteria
Summary of the rules and criteria required by the component data file and to be used
in this notice.
Calculations
This chiefly comprises:
-
Justification of the models used for the geometry and loadings.
-
Description and justification of the calculation methods used. In this latter case,
the reference used to check the analytical and/or experimental solutions in the
field of use envisaged will be indicated.
-
Calculated results.
Analysis of the results
This chiefly comprises:
-
Transformation of the calculation results into the form needed to compare them
with the acceptance criteria. In particular, this requires analysis of the
classification of stresses (primary, local primary, secondary, etc.) and the
calculation of equivalent stress intensities .
-
Assessment of stress (or strain) concentration factors and justification.
-
Comparison of stresses, strains, deformations, and use-fractions with applicable
limits.
-
Assessment of uncertainties, accuracy.
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G 74 MA 6 01-05-28 W0.4
-
Assessment of validity of results, justification of models used and simplifications
made.
-
Where applicable, evaluation of the behaviour of the structure with regard to
collapse modes.
Conclusions
Summary of conclusions from analysis.
References to either ITER documents or codes and standards accepted by ITER are possible
to give in the report, if detailed descriptions of analyses, formulas, materials database, etc. are
given in the reference documents.
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G 6. List of codes and standards
-
G A0 GDRD 2, Design Requirements and Guidelines, Level1 (DRG1)
-
G A0 MA 1, Load Specification and Combination.
-
G 74 MA 8, Structural Design Criteria for In-vessel Components (SDC-IC)
-
Structural Design Criteria for Magnet (SDC-MC), revision 06.12.2000
-
Design and Construction Rules for Mechanical Components of FBR Nuclear
Islands (RCC-MR), June 1985 Edition, Paris.
-
ASME Boiler and Pressure Vessel Code, 1995 Edition, Section VIII Division 2,
Alternative rules. (Rules for Construction of Pressure Vessels), The American
Society of Mechanical Engineers, New York, 1995.
-
ASME Boiler and Pressure Vessel Code, 1995 Edition, Section III Division 1
(Rules for Construction of Nuclear Power Plant Components), Subsection NC,
Class 2 Components, The American Society of Mechanical Engineers, New York,
1995.
-
ASME Boiler and Pressure Vessel Code, 1995 Edition, Section III Division 1
(Rules for Construction of Nuclear Power Plant Components), Subsection NF,
Component Supports, The American Society of Mechanical Engineers, New
York, 1995.
-
Chemical Plant and Petroleum Refinery Piping (ASME B31.3 - 1990), The
American Society of Mechanical Engineers, New York
-
Valves - Flanged, Threaded, and Welding End (ASME B16.34 - 1988), The
American Society of Mechanical Engineers, New York
-
Horizontal End Suction Centrifugal Pumps for Chemical Processes (ASME
B73.1M - 1991)," The American Society of Mechanical Engineers, New York.
-
Vertical In-Line Centrifugal Pumps for Chemical Processes (ASME B73.2M 1991)," The American Society of Mechanical Engineers, New York.
-
Building Code Requirements for Reinforced Concrete (ACI 318M-89) (Revised
1992)," American Concrete Institute, Detroit, 1992.
-
Code Requirements for Nuclear Safety Related Concrete Structures (ACI 34990)," American Concrete Institute, Detroit, 1990.
-
Uniform Building Code, 1994 Edition, International Conference of Building
Officials, Whittier, California.
-
AISC Manual of Steel Construction Ð Allowable Stress Design, Ninth Edition,
American Institute of Steel Construction, Inc., Chicago, 1989.
-
AISC Specification for Structural Steel Buildings - Allowable Stress Design and
Plastic Design, June 1, 1989, with Commentary, American Institute of Steel
Construction, Inc., Chicago, 1989.
Structural Design Criteria
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