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ASTM C781-08

(Practice)

Standard Practice for Testing Graphite and Boronated Graphite Materials for High-Temperature Gas-Cooled Nuclear Reactor Components

Standard Practice for Testing Graphite and Boronated Graphite Materials for High-Temperature Gas-Cooled Nuclear Reactor Components

SIGNIFICANCE AND USE
Property data obtained with the recommended test methods identified herein may be used for research and development, design, manufacturing control, specifications, performance evaluation, and regulatory statutes pertaining to high temperature gas-cooled reactors.
The test methods are applicable primarily to specimens in the non-irradiated and non-oxidized state. Many are also applicable to specimens in the irradiated or oxidized state, or both, provided the specimens meet all requirements of the test method. The user is cautioned to consider the instructions given in the test methods.
Additional test methods are in preparation and will be incorporated. The user is cautioned to employ the latest revision.
SCOPE
1.1 This practice covers the test methods for measuring the properties of graphite and boronated graphite materials. These properties may be used for the design and evaluation of high-temperature gas-cooled reactor components.
1.2 The test methods referenced herein are applicable to materials used for replaceable and permanent components as defined in Section 7 and Section 9, and includes fuel elements; removable reflector elements and blocks; permanent side reflector elements and blocks; core support pedestals and elements; control rod, reserve shutdown, and burnable poison compacts; and neutron shield material.
1.3 This practice includes test methods that have been selected from existing ASTM standards, ASTM standards that have been modified, and new ASTM standards that are specific to the testing of materials listed in 1.2. Comments on individual test methods for graphite and boronated graphite components are given in Sections 8 and 10, respectively. The test methods are summarized in Tables 1 and 2.
1.4 The values stated in SI units are to be regarded as standard. The values given in parentheses are for information only.
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.
TABLE 1 Summary of Test Methods for Graphite Components
Note—Designations under preparation will be added when approved.  Fuel, Removable Reflector,
and Core Support Elements;
Pebble Bed Reflector,
Key and Sleeves;
and Dowel PinsPermanent Side
Reflector Elements
and Dowel PinsCore Support Pedestals
and Dowels Fabrication  As Manufactured Bulk DensityC838C838C838 Mechanical Properties  Compressive StrengthC695C695C695  Tensile PropertiesC749AC749AC749A  Poisson’s RatioE132BE132BE132B  Flexural StrengthC651AC651AC651A  Fracture ToughnessBBB  Modulus of ElasticityC747C747C747 Physical Properties  Bulk Density–Machined SpecimensC559C559C559  Surface Area (BET)C1274C1274C1274  PermeabilityC577A,BC577A,BC577A,B  Apparent PorosityC1039C1039C1039  Spectroscopic AnalysisBBB  Electrical ResistivityC611C611C611 Thermal Properties  Linear Thermal ExpansionE228A  Thermal ConductivityE1461AE1461AE1461A Chemical Properties  Oxidative Mass LossC1179BC1179BC1179B  Sulfur ConcentrationC816C816C816  Ash ContentC561AC561AC561A  Equivalent Boron ContentC1233AC1233AC
A Modification of this test method is required. See Section 8 for details.
B New test methods are required. See Section 8 for details.
C There is no identified need for determining this property.
TABLE 2 Summary of Test Methods for Boronated Graphite Components
Note—Designations under preparation will be added when approved.  CompactsNeutron
Shield
Material Control
RodBurnable
PoisonReserve
Shutdown Bulk DensityC838C838C838D4292 Linear Thermal ExpansionAE228AE228AB Particle SizeCCCD2862 Mechanical Strength:  Compressive StrengthC695AC695AC695AB  Impact PerformanceBBBC Chemical Properties:  Sulfur ConcentrationCCCC  Hafnium ConcentrationCCCC  Relative Oxidation RateCCCC Boron Analysis:  Total ...

General Information

Status
Historical
Publication Date
31-Aug-2008
ICS
27.120.10 - Reactor engineering
Technical Committee
D02 - Petroleum Products, Liquid Fuels, and Lubricants
Drafting Committee
D02.F0 - Manufactured Carbon and Graphite Products
Current Stage
Ref Project

Relations

Replaces
ASTM C781-02 - Standard Practice for Testing Graphite and Boronated Graphite Components for High-Temperature Gas-Cooled Nuclear Reactors
Effective Date
01-Sep-2008
Replaced By
ASTM C781-08(2014) - Standard Practice for Testing Graphite and Boronated Graphite Materials for High-Temperature Gas-Cooled Nuclear Reactor Components
Effective Date
01-May-2014
Referred By
ASTM C714-17 - Standard Test Method for Thermal Diffusivity of Carbon and Graphite by Thermal Pulse Method
Effective Date
01-Sep-2008
Referred By
ASTM D7301-21 - Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose
Effective Date
01-Sep-2008
Referred By
ASTM D7846-21 - Standard Practice for Reporting Uniaxial Strength Data and Estimating Weibull Distribution Parameters for Advanced Graphites
Effective Date
01-Sep-2008
Referred By
ASTM D7219-19 - Standard Specification for Isotropic and Near-isotropic Nuclear Graphites
Effective Date
01-Sep-2008

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Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation: C781 − 08 AnAmerican National Standard
Standard Practice for
Testing Graphite and Boronated Graphite Materials for High-
1
Temperature Gas-Cooled Nuclear Reactor Components
This standard is issued under the fixed designation C781; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope* ments of Manufactured Carbon and Graphite Articles
C561 Test Method for Ash in a Graphite Sample
1.1 This practice covers the test methods for measuring the
C577 Test Method for Permeability of Refractories
properties of graphite and boronated graphite materials. These
C611 TestMethodforElectricalResistivityofManufactured
properties may be used for the design and evaluation of
Carbon and Graphite Articles at Room Temperature
high-temperature gas-cooled reactor components.
C625 Practice for Reporting Irradiation Results on Graphite
1.2 The test methods referenced herein are applicable to
C651 Test Method for Flexural Strength of Manufactured
materials used for replaceable and permanent components as
CarbonandGraphiteArticlesUsingFour-PointLoadingat
defined in Section 7 and Section 9, and includes fuel elements;
Room Temperature
removable reflector elements and blocks; permanent side
C695 Test Method for Compressive Strength of Carbon and
reflector elements and blocks; core support pedestals and
Graphite
elements; control rod, reserve shutdown, and burnable poison
C709 Terminology Relating to Manufactured Carbon and
compacts; and neutron shield material.
Graphite
1.3 This practice includes test methods that have been
C747 Test Method for Moduli of Elasticity and Fundamental
selected from existing ASTM standards, ASTM standards that
Frequencies of Carbon and Graphite Materials by Sonic
have been modified, and newASTM standards that are specific
Resonance
tothetestingofmaterialslistedin1.2.Commentsonindividual
C749 Test Method for Tensile Stress-Strain of Carbon and
test methods for graphite and boronated graphite components
Graphite
are given in Sections 8 and 10, respectively. The test methods
C769 Test Method for Sonic Velocity in Manufactured
are summarized in Tables 1 and 2.
Carbon and Graphite Materials for Use in Obtaining
1.4 The values stated in SI units are to be regarded as
Young’s Modulus
standard. The values given in parentheses are for information
C816 Test Method for Sulfur in Graphite by Combustion-
only.
Iodometric Titration Method
1.5 This standard does not purport to address all of the C838 Test Method for Bulk Density of As-Manufactured
safety concerns, if any, associated with its use. It is the Carbon and Graphite Shapes
responsibility of the user of this standard to establish appro- C1039 Test Methods for Apparent Porosity, Apparent Spe-
priate safety and health practices and determine the applica- cific Gravity, and Bulk Density of Graphite Electrodes
bility of regulatory limitations prior to use.
C1179 Test Method for Oxidation Mass Loss of Manufac-
tured Carbon and Graphite Materials in Air
2. Referenced Documents
C1233 Practice for Determining Equivalent Boron Contents
2
of Nuclear Materials
2.1 ASTM Standards:
C1274 Test Method forAdvanced Ceramic Specific Surface
C559 Test Method for Bulk Density by Physical Measure-
Area by Physical Adsorption
D346 Practice for Collection and Preparation of Coke
1
Samples for Laboratory Analysis
This practice is under the jurisdiction of ASTM Committee D02 on Petroleum
Products and Lubricants and is the direct responsibility of Subcommittee D02.F0 on
D1193 Specification for Reagent Water
Manufactured Carbon and Graphite Products.
D2854 Test Method for Apparent Density of Activated
Current edition approved Sept. 1, 2008. Published October 2008. Originally
Carbon
approved in 1977. Last previous edition approved in 2002 as C781–02. DOI:
10.1520/C0781-08.
D2862 Test Method for Particle Size Distribution of Granu-
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
lar Activated Carbon
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
D3104 Test Method for Softening Point of Pitches (Mettler
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. Softening Point Method)
*A Summary of Changes section appears at the end of this standard
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C781 − 08
TABLE 1 Summary of Test Methods for Graphite Components
NOTE 1—Designations under preparation will be added when approved.
Fuel, Removable Reflector,
and Cor
...

This document is not anASTM standard and is intended only to provide the user of anASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
An American National Standard
Designation:C 781–02 Designation: C 781 – 08
Standard Practice for
Testing Graphite and Boronated Graphite
ComponentsMaterials for High-Temperature Gas-Cooled
1
Nuclear Reactor Components
This standard is issued under the fixed designation C 781; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope
1.1This practice covers the test methods for measuring those properties of graphite and boronated graphite materials that may
be used for the design and evaluation of high-temperature gas-cooled reactors. *
1.1 This practice covers the test methods for measuring the properties of graphite and boronated graphite materials. These
properties may be used for the design and evaluation of high-temperature gas-cooled reactor components.
1.2 The test methods referenced herein are applicable to materials used for replaceable and permanent components as defined
in Section 7 and Section 9, and includes fuel elements; removable reflector elements and blocks; permanent side reflector elements
and blocks; core support pedestals and elements; control rod, reserve shutdown, and burnable poison compacts; and neutron shield
material.
1.3 This practice includes test methods that have been selected from existingASTM standards,ASTM standards that have been
modified, and newASTM standards that are specific to the testing of materials listed in 1.2. Comments on individual test methods
for graphite and boronated graphite components are given in Sections 8 and 10, respectively. The test methods are summarized
in Table 1 and Table 2Tables 1 and 2.
1.4
1.4 The values stated in SI units are to be regarded as standard. The values given in parentheses are for information only.
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility
of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory
limitations prior to use.
2. Referenced Documents
2
2.1 ASTM Standards:
C 559 Test Method for Bulk Density by Physical Measurements of Manufactured Carbon and Graphite Articles
2
C560Test Methods for Chemical Analysis of Graphite 561 Test Method for Ash in a Graphite Sample
2
C561Test Method for Ash in a Graphite Sample
C 577 Test Method for Permeability of Refractories
C 611 Test Method for Electrical Resistivity of Manufactured Carbon and Graphite Articles at Room Temperature
2
C 625Practice for Reporting Irradiation Results on Graphite
C626Methods for Estimating the Thermal Neutron Absorption Cross Section of Nuclear Graphite Practice for Reporting
Irradiation Results on Graphite
C 651 Test Method for Flexural Strength of Manufactured Carbon and Graphite Articles Using Four-Point Loading at Room
Temperature
C 695 Test Method for Compressive Strength of Carbon and Graphite
C 709 Terminology Relating to Manufactured Carbon and Graphite
C 747 Test Method for Moduli of Elasticity and Fundamental Frequencies of Carbon and Graphite Materials by Sonic
Resonance
C 749 Test Method for Tensile Stress-Strain of Carbon and Graphite
2
C816Test Method for Sulfur in Graphite by Combustion-Iodometric Titration Method 769 Test Method for Sonic Velocity in
1
This practice is under the jurisdiction of ASTM Committee D02 on Petroleum Products and Lubricants and is the direct responsibility of Subcommittee D02.F0 on
Manufactured Carbon and Graphite Products.
Current edition approved Dec. 10, 2002. Published April 2003. Originally approved in 1977. Last previous edition approved in 1996 as C781–96.
Current edition approved Sept. 1, 2008. Published October 2008. Originally approved in 1977. Last previous edition approved in 2002 as C 781–02.
2
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at service@astm.org. For Annual Book of ASTM Standards
, Vol 05.05.volume information, refer to the standard’s Document Summary page on the ASTM website.
*A Summary of Changes section appears at the end of this standard.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
C781–08
TABLE 1 Summary of Test Methods for Graphite Components
NOTE—Designations under preparat
...

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4.1 The purpose of this guide is to provide general guidelines for the design and operation of hot cell equipment to ensure longevity and reliability throughout the period of service.  
4.2 It is intended that this guide record the general conditions and practices that experience has shown is necessary to minimize equipment failures and maximize the effectiveness and utility of hot cell equipment. It is also intended to alert designers to those features that are highly desirable for the selection of equipment that has proven reliable in high radiation environments.  
4.3 This guide is intended as a supplement to other standards, and to federal and state regulations, codes, and criteria applicable to the design of equipment intended for hot cell use.  
4.4 This guide is intended to be generic and to apply to a wide range of types and configurations of hot cell equipment.
SCOPE
1.1 Intent:  
1.1.1 The intent of this guide is to provide general design and operating considerations for the safe and dependable operation of remotely operated hot cell equipment. Hot cell equipment is hardware used to handle, process, or analyze nuclear or radioactive material in a shielded room. The equipment is placed behind radiation shield walls and cannot be directly accessed by the operators or by maintenance personnel because of the radiation exposure hazards. Therefore, the equipment is operated remotely, either with or without the aid of viewing.  
1.1.2 This guide may apply to equipment in other radioactive remotely operated facilities such as suited entry repair areas, canyons or caves, but does not apply to equipment used in commercial power reactors.  
1.1.3 This guide does not apply to equipment used in gloveboxes.  
1.2 Applicability:  
1.2.1 This guide is intended for persons who are tasked with the planning, design, procurement, fabrication, installation, or testing of equipment used in remote hot cell environments.  
1.2.2 The equipment will generally be used over a long-term life cycle (for example, in excess of two years), but equipment intended for use over a shorter life cycle is not excluded.  
1.2.3 The system of units employed in this standard is the metric unit, also known as SI Units, which are commonly used for International Systems, and defined by IEEE/ASTM SI 10: American National Standard for Use of the International System of Units (SI): The Modern Metric System.  
1.3 Caveats:  
1.3.1 This guide does not address considerations relating to the design, construction, operation, or safety of hot cells, caves, canyons, or other similar remote facilities. This guide deals only with equipment intended for use in hot cells.  
1.3.2 Specific design and operating considerations are found in other ASTM documents.  
1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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ASTM
ASTM C1615/C1615M-17(2022)(Guide)
Standard Guide for Mechanical Drive Systems for Remote Operation in Hot Cell Facilities

SIGNIFICANCE AND USE
4.1 Mechanical drive systems operability and long-term integrity are concerns that should be addressed primarily during the design phase; however, problems identified during fabrication and testing should be resolved and the changes in the design documented. Equipment operability and integrity can be compromised during handling and installation sequences. For this reason, the subject equipment should be handled and installed under closely controlled and supervised conditions.  
4.2 This standard is intended as a supplement to other standards, and to federal and state regulations, codes, and criteria applicable to the design of equipment intended for this use.  
4.3 This standard is intended to be generic and to apply to a wide range of types and configurations of mechanical drive systems.
SCOPE
1.1 Intent:  
1.1.1 The intent of this standard is to provide general guidelines for the design, selection, quality assurance, installation, operation, and maintenance of mechanical drive systems used in remote hot cell environments. The term mechanical drive systems used herein, encompasses all individual components used for imparting motion to equipment systems, subsystems, assemblies, and other components. It also includes complete positioning systems and individual units that provide motive power and any position indicators necessary to monitor the motion.  
1.2 Applicability:  
1.2.1 This standard is intended to be applicable to equipment used under one or more of the following conditions:  
1.2.1.1 The materials handled or processed constitute a significant radiation hazard to man or to the environment.
1.2.1.2 The equipment will generally be used over a long-term life cycle (for example, in excess of two years), but equipment intended for use over a shorter life cycle is not excluded.
1.2.1.3 The equipment can neither be accessed directly for purposes of operation or maintenance, nor can the equipment be viewed directly, for example, without radiation shielding windows, periscopes, or a video monitoring system (Guides C1572 and C1661).  
1.2.2 The values stated in either SI units or inch-pound units are to be regarded separately as standard. The values stated in each system may not be exact equivalents; therefore, each system shall be used independently of the other. Combining values from the two systems may result in non-conformance with the standard.  
1.3 User Caveats:  
1.3.1 This standard is not a substitute for applied engineering skills, proven practices and experience. Its purpose is to provide guidance.
1.3.1.1 The guidance set forth in this standard relating to design of equipment is intended only to alert designers and engineers to those features, conditions, and procedures that have been found necessary or highly desirable to the design, selection, operation and maintenance of mechanical drive systems for the subject service conditions.
1.3.1.2 The guidance set forth results from discoveries of conditions, practices, features, or lack of features that were found to be sources of operational or maintenance problems, or causes of failure.  
1.3.2 This standard does not supersede federal or state regulations, or both, and codes applicable to equipment under any conditions.  
1.3.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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ASTM
ASTM C1725-17(2022)(Guide)
Standard Guide for Hot Cell Specialized Support Equipment and Tools

SIGNIFICANCE AND USE
4.1 This guide is relevant to the design of specialized support equipment and tools that are remotely operated, maintained, or viewed through shielding windows, or combinations thereof, or by other remote viewing systems.  
4.2 Hot cells contain substances and processes that may be extremely hazardous to personnel or the external environment, or both. Process safety and reliability are improved with successful design, installation, and operation of specialized mechanical and support equipment.  
4.3 Use of this guide in the design of specialized mechanical and support equipment can reduce costs, improve productivity, reduce failed hardware replacement time, and provide a standardized design approach.
SCOPE
1.1 Intent:  
1.1.1 This guide presents practices and guidelines for the design and implementation of equipment and tools to assist assembly, disassembly, alignment, fastening, maintenance, or general handling of equipment in a hot cell. Operating in a remote hot cell environment significantly increases the difficulty and time required to perform a task compared to completing a similar task directly by hand. Successful specialized support equipment and tools minimize the required effort, reduce risks, and increase operating efficiencies.  
1.2 Applicability:  
1.2.1 This guide may apply to the design of specialized support equipment and tools anywhere it is remotely operated, maintained, and viewed through shielding windows or by other remote viewing systems.  
1.2.2 Consideration should be given to the need for specialized support equipment and tools early in the design process.  
1.2.3 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.  
1.3 Caveats:  
1.3.1 This guide is generic in nature and addresses a wide range of remote working configurations. Other acceptable and proven international configurations exist and provide options for engineer and designer consideration. Specific designs are not a substitute for applied engineering skills, proven practices, or experience gained in any specific situation.  
1.3.2 This guide does not supersede federal or state regulations, or both, or codes applicable to equipment under any conditions.  
1.3.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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ASTM
ASTM E2006-22(Guide)
Standard Guide for Benchmark Testing of Light Water Reactor Calculations

SIGNIFICANCE AND USE
4.1 This guide deals with the difficult problem of benchmarking neutron transport calculations carried out to determine fluences for plant specific reactor geometries. The calculations are necessary for fluence determination in locations important for material radiation damage estimation and which are not accessible to measurement. Typically, the most important application of such calculations is the estimation of fluence within the reactor vessel of operating light water reactors (LWR) to provide accurate estimates of the irradiation embrittlement of the base and weld metal in the vessel. The benchmark procedure must not only prove that calculations give reasonable results but that their uncertainties are propagated with due regard to the sensitivities of the different input parameters used in the transport calculations. Benchmarking is achieved by building up data bases of benchmark experiments that have different influences on uncertainty propagation. For example, in simple vessel wall mockups where measurements are made within a simulated reactor vessel wall, the integral effect of uncertainties in iron cross sections (absorption and elastic and inelastic scattering) are dominant and have been bounded by the agreement between calculation and measurement. For more complicated integral benchmarks, other factors such as: uncertainties in the distribution of fission sources, geometry, the energy-dependent cross sections, and the angular scattering distribution for elemental components of major materials in the neutron field (such as water and iron) may all be important uncertainty contributors. This guide describes general procedures for using neutron fields with known characteristics to corroborate the calculational methodology and nuclear data used to derive neutron field information from measurements of neutron sensor response.  
4.2 The bases for benchmark field referencing are usually irradiations performed in standard neutron fields with well-known energy spe...
SCOPE
1.1 This guide covers general approaches for benchmarking neutron transport calculations for pressure vessel surveillance programs in light water reactor systems. A companion guide (Guide E2005) covers use of benchmark fields for testing neutron transport calculations and cross sections in well controlled environments. This guide covers experimental benchmarking of neutron fluence calculations (or calculations of other exposure parameters such as dpa) in more complex geometries relevant to reactor pressure vessel surveillance. Particular sections of the guide discuss: the use of well-characterized benchmark neutron fields to provide an indication of the accuracy of the calculational methods and nuclear data when applied to typical cases; and the use of plant specific measurements to indicate bias in individual plant calculations. Use of these two benchmark techniques will serve to limit plant-specific calculational uncertainty, and, when combined with analytical uncertainty estimates for the calculations, will provide uncertainty estimates for reactor fluences with a higher degree of confidence.  
1.2 Although this guide and the companion guide, Guide E2005, are focused on power reactors, the principle of this guide is also applicable to non-power light water reactor pressure vessel surveillance programs.  
1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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ASTM
ASTM D7727-21(Practice)
Standard Practice for Calculation of Dose Equivalent Xenon (DEX) for Radioactive Xenon Fission Products in Reactor Coolant

SIGNIFICANCE AND USE
5.1 Each power reactor has a specific DEX value that is their technical requirement limit. These values may vary from about 200 to about 900 μCi/g based upon the height of their plant vent, the location of the site boundary, the calculated reactor coolant activity for a condition of 1 % fuel defects, and general atmospheric modeling that is ascribed to that particular plant site. Should the DEX measured activity exceed the technical requirement limit, the plant enters an LCO requiring action on plant operation by the operators.  
5.2 The determination of DEX is performed in a similar manner to that used in determining DEI, except that the calculation of DEX is based on the acute dose to the whole body and considers the noble gases 85mKr, 85Kr, 87Kr, 88Kr, 131mXe, 133mXe, 133Xe, 135mXe, 135Xe, and 138Xe which are significant in terms of contribution to whole body dose.  
5.3 It is important to note that only fission gases are included in this calculation, and only the ones noted in Table 1. For example 83mKr is not included even though its half-life is 1.86 hours. The reason for this is that this radionuclide cannot be easily determined by gamma spectrometry (low energy X-rays at 32 and 9 keV) and its dose consequence is vanishingly small compared to the other, more prevalent krypton radionuclides.  
5.4 Activity from 41Ar, 19F, 16N, and 11C, all of which predominantly will be in gaseous forms in the RCS, are not included in this calculation.  
5.5 If a specific noble-gas radionuclide is not detected, it should be assumed to be present at the minimum-detectable activity. The determination of dose-equivalent Xe-133 shall be performed using effective dose-conversion factors for air submersion listed in Table III.1 of EPA Federal Guidance Report No. 12,3 or the average gamma-disintegration energies as provided in ICRP Publication 38 (“Radionuclide Transformations”) or similar source.
SCOPE
1.1 This practice applies to the calculation of the dose equivalent to 133Xe in the reactor coolant of nuclear power reactors resulting from the radioactivity of all noble gas fission products.  
1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.  
1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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