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ASTM C781-96

(Practice)

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

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

SCOPE
1.1 This 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.
1.2 The test methods referenced herein are applicable to materials used for replaceable and permanent components as defined in Section 7 and include fuel and removable reflector elements; target elements and insulators; permanent side reflector elements; 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 for boronated graphite components are given in Sections 8 and 10, respectively. The test methods are summarized in Tables 1 and 2.
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 and health practices and determine the applicability of regulatory limitations prior to use.

General Information

Status
Historical
Publication Date
31-Dec-1995
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

Replaced By
ASTM C781-02 - Standard Practice for Testing Graphite and Boronated Graphite Components for High-Temperature Gas-Cooled Nuclear Reactors
Effective Date
10-Dec-2002
Referred By
ASTM D7219-19 - Standard Specification for Isotropic and Near-isotropic Nuclear Graphites
Effective Date
01-Jan-1996
Referred By
ASTM D7301-21 - Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose
Effective Date
01-Jan-1996
Referred By
ASTM C714-17 - Standard Test Method for Thermal Diffusivity of Carbon and Graphite by Thermal Pulse Method
Effective Date
01-Jan-1996
Referred By
ASTM D7846-21 - Standard Practice for Reporting Uniaxial Strength Data and Estimating Weibull Distribution Parameters for Advanced Graphites
Effective Date
01-Jan-1996

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ASTM C781-96 - Standard Practice for Testing Graphite and Boronated Graphite Components for High-Temperature Gas-Cooled Nuclear ReactorsASTM C781-96 - Standard Practice for Testing Graphite and Boronated Graphite Components for High-Temperature Gas-Cooled Nuclear Reactors
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ASTM C781-96 - Standard Practice for Testing Graphite and Boronated Graphite Components for High-Temperature Gas-Cooled Nuclear Reactors
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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.
An American National Standard
Designation: C 781 – 96
Standard Practice for
Testing Graphite and Boronated Graphite Components for
High-Temperature Gas-Cooled Nuclear Reactors
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 (e) indicates an editorial change since the last revision or reapproval.
1. Scope sorption Cross Section of Nuclear Graphite
C 651 Test Method for Flexural Strength of Manufactured
1.1 This practice covers the test methods for measuring
Carbon and GraphiteArticles Using Four-Point Loading at
those properties of graphite and boronated graphite materials
Room Temperature
that may be used for the design and evaluation of high-
C 695 Test Method for Compressive Strength of Carbon
temperature gas-cooled reactors.
and Graphite
1.2 The test methods referenced herein are applicable to
C 709 Terminology Relating to Manufactured Carbon and
materials used for replaceable and permanent components as
Graphite
defined in Section 7 and include fuel and removable reflector
C 747 Test Method for Moduli of Elasticity and Fundamen-
elements; target elements and insulators; permanent side re-
tal Frequencies of Carbon and Graphite Materials by Sonic
flector elements; core support pedestals and elements; control
Resonance
rod, reserve shutdown, and burnable poison compacts; and
C 749 Test Method for Tensile Stress-Strain of Carbon and
neutron shield material.
Graphite
1.3 This practice includes test methods that have been
C 816 Test Method for Sulfur in Graphite by Combustion-
selected from existing ASTM standards, ASTM standards that
Iodometric Titration Method
have been modified, and newASTM standards that are specific
C 838 Test Method for Bulk Density of As-Manufactured
tothetestingofmaterialslistedin1.2.Commentsonindividual
Carbon and Graphite Shapes
test methods for graphite and boronated graphite components
C 1179 Test Method for Oxidative Mass Loss of Manufac-
are given in Sections 8 and 10, respectively. The test methods
turered Carbon and Graphite Materials in Air
are summarized in Table 1 and Table 2.
C 1251 Test Method for Determination of Specific Surface
1.4 This standard does not purport to address all of the
Areas ofAdvanced Ceramic Materials by GasAdsorption
safety concerns, if any, associated with its use. It is the
D 2854 Test Method for Apparent Density of Activated
responsibility of the user of this standard to establish appro-
Carbon
priate safety and health practices and determine the applica-
D 2862 Test Method for Particle Size Distribution of
bility of regulatory limitations prior to use.
Granular Activated Carbon
2. Referenced Documents
D 4292 Test Method for Vibrated Bulk Density of Calcined
Petroleum Coke
2.1 ASTM Standards:
E 132 Test Method for Poisson’s Ratio at Room Tempera-
C 559 Test Method for Bulk Density by Physical Measure-
ture
ments of Manufactured Carbon and Graphite Articles
E 228 Test Method for Linear Thermal Expansion of Solid
C 560 Test Methods for Chemical Analysis of Graphite
Materials with a Vitreous Silica Dilatometer
C 561 Test Method for Ash in a Graphite Sample
E 261 Practice for Determining Neutron Fluence Rate, Flu-
C 577 Test Method for Permeability of Refractories
ence, and Spectra by Radioactivation Techniques
C 625 Practice for Reporting Irradiation Results on Graph-
E 1461 Test Method for Thermal Diffusivity of Solids by
ite
the Flash Method
C 626 Methods for Estimating the Thermal Neutron Ab-
3. Terminology
3.1 Definition:
This practice is under the jurisdiction of ASTM Committee D02 on Petroleum
Products and Lubricants and is the direct responsibility of Subcommittee D02.F on
Manufactured Carbon and Graphite Products . Discontinued; see 1985 Annual Book of ASTM Standards, Vol 15.01.
Current edition approved Nov. 10, 1996. Published December 1996. Originally Annual Book of ASTM Standards, Vol 05.02.
published as C 781 – 77. Last previous edition C 781 – 93. Annual Book of ASTM Standards, Vol 03.01.
2 7
Annual Book of ASTM Standards, Vol 05.05. Annual Book of ASTM Standards, Vol 14.02.
3 8
Annual Book of ASTM Standards, Vol 15.01. Annual Book of ASTM Standards, Vol 12.02.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
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.
C 781
TABLE 1 Summary of Test Methods for Graphite Components
NOTE 1—Designations under preparation will be added as editorial changes when approved.
Fuel, Removable Permanent Core
Reflector, and Core Side Support
Support Elements; Reflector Pedestals
Target Assemblies Elements and Dowel
and Insulators; and and Dowel Pins
Dowel Pins Pins
Bulk Density:
As-Manufactured Shapes C 838 C 838 C 838
Machined Specimens C 559 C 559 C 559
Thermal Properties:
A A A
Linear Thermal Expansion E 228 E 228 E 228
A A A
Thermal Conductivity E 1461 E 1461 E 1461
Mechanical Properties:
Compressive Strength C 695 C 695 C 695
A A A
Tensile Properties C 749 C 749 C 749
A A A
Poisson’s Ratio E 132 E 132 E 132
A A A
Flexural Strength C 651 C 651 C 651
BB B
Fracture Toughness
Modulus of Elasticity C 747 C 747 C 747
Oxidation Related Properties:
B B B
Relative Oxidation Rate C 1179 C 1179 C 1179
Surface Area C 1251 C 1251 C 1251
AB AB AB
Permeability C 577 C 577 C 577
B B B
Catalytic Impurities C 560 C 560 C 560
Sulfur Concentration C 816 C 816 C 816
BB B
Porosity
Neutronic Impurities:
A A A
Ash C 561 C 561 C 561
BB B
Spectroscopic Analysis
A AC
Thermal Absorption Cross C 626 C 626
Section
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
4. Significance and Use
Components
4.1 Properly data obtained with the recommended test
NOTE 1—Designations under preparation will be added as editorial
methods identified herein may be used for research and
changes when approved.
development, design, manufacturing control, specifications,
performance evaluation, and regulatory statutes pertaining to
Compacts
high temperature gas-cooled reactors.
Neutron Shield
Control Burnable Reserve
Material
4.2 The test methods are applicable primarily to specimens
Rod Poison Shutdown
in the unirradiated and unoxidized state. Many are also
Bulk Density C 838 C 838 C 838 D 4292
A A AB applicable to specimens in the irradiated or oxidized state, or
Linear Thermal Expansion E 228 E 228
CCC
Particle Size D 2862 both, provided the specimens meet all requirements of the test
Mechanical Strength:
method. The user is cautioned to consider the instructions
A A A B
Compressive Strength C 695 C 695 C 695
B B B C given in the test methods.
Impact Performance
Chemical Properties: 4.3 Additional test methods are in preparation and will be
CCC C
Catalytic Impurities
incorporated. The user is cautioned to employ the latest
CCC C
Sulfur Concentration
CCC C revision.
Hafnium Concentration
CCC C
Relative Oxidation Rate
Boron Analysis:
5. Sample Selection
CCC C
Total Boron
CCC C
Boron as Oxide 5.1 All test specimens should be selected from materials
D D D D
B C Particle Size D 2862 D 2862 D 2862 D 2862
that are representative of those to be used in the intended
A
Modification of this test method is required. See Section10 for details.
application.
B
There is no identified need for determining this property.
C
New test methods are required. See Section 10 for details.
D
6. Test Reports
Additional test methods are required. See Section10 for details.
6.1 Test results should be reported in accordance with the
3.1.1 Terminology C 709 shall be considered as applying to reporting requirements included in the applicable test method.
the terms used in this practice. Where relevant, information on grade designation, lot number,
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.
C 781
billet number, orientation, and location (position of sample in the target assembly insulators are to provide thermal insulation
the original billet) shall be provided. of the target assemblies from the fuel or removable reflector
6.2 Information on specimen irradiation conditions shall be elements and a physical constraint for the flow of coolant gas.
reported in accordance with Practices C 625 and E 261 or 7.3 Permanent Side Reflector Elements:
referenced to source information of equivalent content. 7.3.1 Apermanent side reflector element is a graphite block
that is designed to remain permanently in the core but may be
GRAPHITE COMPONENTS
removed for inspection and replacement, if necessary. A
permanent side reflector element contains channels for align-
7. Description and Function
ment dowel pins. It may also contain channels for neutron flux
7.1 Fuel and Removable Reflector Elements:
control materials (boronated steel pins) and nuclear instrumen-
7.1.1 A fuel element is a removable graphite element that
tation,andrecessedareasalongitslengthonitsouterperiphery
contains channels for the passage of coolant gas, the fuel
to provide channels for the passage of coolant gas between the
material, the alignment dowel pins, and the insertion of a
element and the metallic lateral restraint for the reactor core.
handling machine pickup head. A fuel element may also
7.3.2 The permanent side reflector elements encircle the
contain channels for reactivity control material (control rods),
active (fuel) elements and passive (removable reflector) ele-
reserve shutdown compacts, and burnable poison compacts,
ments of the reactor core and serve multiple functions, includ-
graphite target assemblies and insulators, and nuclear instru-
ing (a) vertical and lateral mechanical support for the perma-
mentation.
nent side reflector elements above and beside them, (b) lateral
7.1.2 The fuel elements serve multiple functions, including
mechanical support for the fuel, removable reflector, and core
(a)verticalandlateralmechanicalsupportforthefuelelements
support elements, (c) moderation of fast neutrons within the
and removable reflector elements above and adjacent to them,
reflector region, (d) reflection of thermal neutrons back into the
and for the fuel, reactivity control materials, target assemblies
core region, and (e) support, guide, and containment of nuclear
and insulators, and nuclear instrumentation within them, (b)
instrumentation and neutron flux control materials (boronated
moderation of fast neutrons within the core region, (c) a
steel pins) for reducing the neutron flux to metallic structures
thermal reservoir and conductor for nuclear heat generated in
outside the permanent side reflector boundary.
the fuel, (d) a physical constraint for the flow of coolant gases,
7.4 Core Support Pedestals and Elements:
and (e) a guide for and containment of fuel material, reactivity
7.4.1 A core support pedestal is a graphite column that is
control materials, target assemblies and insulators, and nuclear
designedtoremainpermanentlyinthecorebutcanberemoved
instrumentation.
for inspection and replacement, if necessary. A core support
7.1.3 Aremovable reflector element is a removable graphite
pedestal has a central reduced cross-section (dog bone shape)
element that contains channels for the alignment dowel pins
that at its upper end contains channels for the passage of
and the insertion of a handling machine pickup head. A
coolant gas, alignment dowel pins, and the insertion of a
removable reflector element may also contain channels for the
handling machine pickup head, and at its lower end contains a
passage of coolant gas, reactivity control materials (control
recessed region for locating it with respect to the metallic
rods), neutron flux control materials (neutron shield materials),
structure that supports the graphite core support assembly. A
target assemblies and insulators, and nuclear instrumentation.
core support element is a graphite element that contains
7.1.4 The primary function of the removable reflector ele-
channels for alignment dowel pins and the insertion of a
ments that are located at the boundaries of the active reactor
handling machine pickup head.The core support elements may
core (fuel elements) is to provide for moderation of fast
also contain channels for the passage of coolant gas, neutron
neutronsescapingfromandreflectionofthermalneutronsback
flux control materials, and nuclear instrumentation.
into the active core region.
7.4.2 The primary function of the core support pedestals is
7.1.5 Except for support, guide, and containment of fuel
to provide for vertical mechanical support for core support
material, removable reflector elements may also serve any of
elements and permanent side reflector elements above them. In
the functions listed in 7.1.2.
addition, core support pedestals provide for lateral mechanical
7.2 Target Assemblies and Insulators:
support for adjacent core support pedestals and permanent side
7.2.1 A target assembly is a removable graphite canister
reflector elements and physical constraint for the flow of
consisting of an inner and outer annular sleeve and bottom and
coolant gases. The primary function of the core support
top end caps, that contains an annular channel for target
elements is to provide for vertical mechanical support for core
materials and a central channel for the passage of cooling gas.
support, fuel, and removable reflector elements above them. In
A target assembly insulator is an annular sleeve containing a
addition, core support elements provide for lateral mechanical
recessed area around its outer circumference that provides a
support for adjacent core support and permanent side reflector
thermal insulating gap between the insulating sleeve and the
elementsandmayprovideforthephysicalconstraintofcoolant
adjoining element channel. The inner circumference of the
gases and for the support, guide, and containment of neutron
insulating sleeve provides a channel for the passage of coolant
flux control materials and nuclear instrumentation.
gas between the insulator and the target assembly.
8. Test Methods
7.2.2 The primary function of the target asemblies is to
provide support, guide, and containment of target materials 8.1 Bulk Density:
used for the production of special radioisotopes and a physical 8.1.1 Determine bulk density on as-manufactured
...

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1.3 This guide does not attempt to address maintenance or service procedures related to the gauge.  
1.4 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.  
1.5 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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This guide offers an organized collection of information or a series of options and does not recommend a specific course of action. This document cannot replace education or experience and should be used in conjunction with professional judgment. Not all aspects of this guide may be applicable in all circumstances. This ASTM standard is not intended to represent or replace the standard of care by which the adequacy of a given professional service must be judged, nor should this document be applied without consideration of a project’s many unique aspects. The word “Standard” in the title of this document has been approved through ASTM consensus process.  
1.7 All observed and calculated values shall conform to the guidelines for significant digits and rounding established in practice D6026.  
1.7.1 The method used to specify how data are collected, calculated, or recorded in this standard is not directly related to the accuracy to which the data can be applied in the design or other uses, or both. How one applies the results obtained using this standard is beyond its scope.  
1.8 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 C1533-15(2022)(Guide)
Standard Guide for General Design Considerations for Hot Cell Equipment

SIGNIFICANCE AND USE
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 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 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 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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