ASTM C1187-20a

Standard Guide for Establishing Surveillance Test Program for Boron-based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in Pool Environment

SIGNIFICANCE AND USE
4.1 The storage of nuclear fuel in high-density storage racks is dependent upon the functionality and integrity of an absorber between the stored fuel assemblies to ensure that the reactivity of the storage configuration does not exceed the K-effective allowed by applicable regulations. A confirmation test may be required to verify the functionality and integrity of the absorber within the racks. If establishing a surveillance program for newly installed or existing absorber material in fuel racks, the following methods are suggested: (a) coupon monitoring program (if coupons are available), (b) in-situ neutron attenuation test, and (c) other applicable in-situ tests such as visual inspection or drag test.  
4.2 This guide provides guidance for establishing and conducting a surveillance program for monitoring the ongoing functionality and integrity of the absorbers.
SCOPE
1.1 This guide provides guidance for establishing a surveillance test program to monitor the performance of boron-based neutron absorbing material systems (absorbers) necessary to maintain sub-criticality in nuclear fuel storage racks in a pool environment. The practices presented in this guide, when implemented, will provide a comprehensive surveillance test program to verify the functionality and integrity of the neutron absorbing material within the storage racks. The performance of a surveillance test program provides added assurance of the safe and effective operation of a high-density storage facility for nuclear fuel. There are several different techniques for surveillance testing of boron-based neutron absorbing materials. This guide focuses on coupon monitoring and in-situ testing.  
1.2 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.  
1.3 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.

General Information

• Status: Published
• Publication Date: 30-Jun-2020
• ICS: 13.280 - Radiation protection
• ICS: 27.120.30 - Fissile materials and nuclear fuel technology
• Technical Committee: C26 - Nuclear Fuel Cycle
• Drafting Committee: C26.03 - Neutron Absorber Materials Specifications

Relations

• Refers: ASTM E8/E8M-24 - Standard Test Methods for Tension Testing of Metallic Materials
• Effective Date: 01-Jan-2024
• Refers: ASTM C859-24 - Standard Terminology Relating to Nuclear Materials
• Effective Date: 01-Jan-2024
• Refers: ASTM E45-18a(2023) - Standard Test Methods for Determining the Inclusion Content of Steel
• Effective Date: 01-Nov-2023
• Refers: ASTM G69-20 - Standard Test Method for Measurement of Corrosion Potentials of Aluminum Alloys
• Effective Date: 01-May-2020
• Refers: ASTM C992-20 - Standard Specification for Boron-based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in Pool Environment
• Effective Date: 01-Jan-2020
• Refers: ASTM G16-13(2019) - Standard Guide for Applying Statistics to Analysis of Corrosion Data
• Effective Date: 15-Feb-2019
• Refers: ASTM E8/E8M-16 - Standard Test Methods for Tension Testing of Metallic Materials
• Effective Date: 15-Jul-2016
• Refers: ASTM C992-16 - Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in a Pool Environment
• Effective Date: 15-Jan-2016
• Refers: ASTM E8/E8M-15 - Standard Test Methods for Tension Testing of Metallic Materials
• Effective Date: 01-Feb-2015
• Refers: ASTM C859-14a - Standard Terminology Relating to Nuclear Materials
• Effective Date: 15-Jun-2014
• Refers: ASTM E2971-14 - Standard Test Method for Determination of Effective Boron-10 Areal Density in Aluminum Neutron Absorbers using Neutron Attenuation Measurements
• Effective Date: 01-Jun-2014
• Refers: ASTM C859-14 - Standard Terminology Relating to Nuclear Materials
• Effective Date: 15-Jan-2014
• Refers: ASTM G16-13 - Standard Guide for Applying Statistics to Analysis of Corrosion Data
• Effective Date: 01-Dec-2013
• Refers: ASTM C859-13a - Standard Terminology Relating to Nuclear Materials
• Effective Date: 01-Jun-2013
• Refers: ASTM E8/E8M-13 - Standard Test Methods for Tension Testing of Metallic Materials
• Effective Date: 01-Jun-2013

Overview

ASTM C1187-20a: Standard Guide for Establishing Surveillance Test Program for Boron-based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in Pool Environment provides a comprehensive framework for developing surveillance test programs. This standard is vital for ensuring the ongoing performance and integrity of boron-based neutron absorbers that are crucial for sub-criticality in high-density nuclear fuel storage racks used in pool environments. Establishing effective surveillance helps confirm that the absorbers maintain adequate neutron attenuation over their service life, thus supporting both regulatory compliance and nuclear safety.

Key Topics

• Surveillance Program Establishment: Guidance on creating structured test programs to monitor boron-based neutron absorbing material systems, whether for new installations or existing racks.
• Testing Techniques:
  • Coupon Monitoring Programs: Periodic retrieval and evaluation of representative specimen coupons, when available.
  • In-situ Neutron Attenuation Tests: Direct testing within the operational environment to assess neutron absorbing functionality.
  • Other In-situ Tests: Visual inspections and mechanical tests (such as drag tests) to detect signs of material degradation.
• Functionality Verification: Regular testing to verify that the neutron absorbers continue to meet performance criteria and regulatory K-effective requirements.
• Degradation Assessment: Evaluation of the impacts of radiation, chemical exposure, corrosion, and mechanical stresses on absorber integrity.
• Documentation: Requirements for detailed recordkeeping, including specimen history, exposure data, and test results to support traceability and regulatory reporting.

Applications

The practical applications of ASTM C1187-20a focus on maintaining nuclear safety through ongoing surveillance methods in facilities utilizing boron-based neutron absorbing materials:

• Nuclear Fuel Storage Facilities: Ensures compliance with safety margins for high-density storage racks in spent fuel pools.
• Safety Analysis and Regulatory Compliance: Supports the justification of continued operation by demonstrating absorber functionality over time via a systematic surveillance program.
• Lifecycle Management: Provides a methodology for early detection of degradation, guiding timely maintenance or replacement decisions.
• Performance Trending: Enables tracking of material performance trends over time, supporting predictive maintenance and optimization of storage rack operation.

Facilities utilizing this standard benefit from reduced risk of exceeded reactivity thresholds and enhanced operational reliability. Comprehensive adoption of these surveillance practices directly supports safe nuclear fuel management and aligns with best practices for spent fuel storage.

Related Standards

Several standards are referenced in ASTM C1187-20a that support or complement surveillance testing programs for boron-based neutron absorbers:

• ASTM C992 - Specification for Boron-based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in Pool Environment
• ASTM C1068 - Guide for Qualification of Measurement Methods by a Laboratory Within the Nuclear Industry
• ASTM E2971 - Test Method for Determination of Effective Boron-10 Areal Density in Aluminum Neutron Absorbers
• ASTM G1, G4, G16, G46, G69 - Guides and Test Methods for Corrosion Testing
• ASTM E6, E8/E8M, E45, E74, E290 - Methods for Mechanical Testing of Materials
• ASTM D412, D430, D518, D813, D1415, D2240, D3183, D4483 - Methods for Physical and Mechanical Testing of Polymers
• ASTM C859 - Terminology Relating to Nuclear Materials

These referenced standards provide the necessary terminology, qualification methods, and measurement techniques crucial for an effective surveillance test program.

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Keywords: boron-based neutron absorbing material systems, neutron absorber surveillance, high-density fuel storage racks, in-situ neutron attenuation testing, coupon monitoring, nuclear pool environment, sub-criticality, absorber integrity, nuclear fuel safety, ASTM C1187-20a.

Standards Content (Sample)

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.
Designation: C1187 − 20a
Standard Guide for
Establishing Surveillance Test Program for Boron-based
Neutron Absorbing Material Systems for Use in Nuclear Fuel
Storage Racks in Pool Environment
This standard is issued under the fixed designation C1187; 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 terial Systems for Use in Nuclear Fuel Storage Racks in
Pool Environment
1.1 This guide provides guidance for establishing a surveil-
C1068 Guide for Qualification of Measurement Methods by
lance test program to monitor the performance of boron-based
a Laboratory Within the Nuclear Industry
neutron absorbing material systems (absorbers) necessary to
D412 Test Methods forVulcanized Rubber andThermoplas-
maintain sub-criticality in nuclear fuel storage racks in a pool
tic Elastomers—Tension
environment. The practices presented in this guide, when
D430 Test Methods for Rubber Deterioration—Dynamic
implemented, will provide a comprehensive surveillance test
Fatigue
program to verify the functionality and integrity of the neutron
D518 Test Method for Rubber Deterioration—Surface
absorbing material within the storage racks. The performance
Cracking (Withdrawn 2007)
of a surveillance test program provides added assurance of the
D813 TestMethodforRubberDeterioration—CrackGrowth
safe and effective operation of a high-density storage facility
D1415 Test Method for Rubber Property—International
for nuclear fuel. There are several different techniques for
Hardness
surveillance testing of boron-based neutron absorbing materi-
D2240 Test Method for Rubber Property—Durometer Hard-
als. This guide focuses on coupon monitoring and in-situ
ness
testing.
D3183 Practice for Rubber—Preparation of Pieces for Test
1.2 This standard does not purport to address all of the
Purposes from Products
safety concerns, if any, associated with its use. It is the
D4483 Practice for Evaluating Precision for Test Method
responsibility of the user of this standard to establish appro-
Standards in the Rubber and Carbon Black Manufacturing
priate safety, health, and environmental practices and deter-
Industries
mine the applicability of regulatory limitations prior to use.
E6 Terminology Relating to Methods of Mechanical Testing
1.3 This international standard was developed in accor-
E8/E8M Test Methods for Tension Testing of Metallic Ma-
dance with internationally recognized principles on standard-
terials
ization established in the Decision on Principles for the
E45 Test Methods for Determining the Inclusion Content of
Development of International Standards, Guides and Recom-
Steel
mendations issued by the World Trade Organization Technical
E74 Practices for Calibration and Verification for Force-
Barriers to Trade (TBT) Committee.
Measuring Instruments
E290 Test Methods for Bend Testing of Material for Ductil-
2. Referenced Documents
ity
2.1 ASTM Standards:
E2971 TestMethodforDeterminationofEffectiveBoron-10
C859 Terminology Relating to Nuclear Materials
Areal Density in Aluminum Neutron Absorbers using
C992 Specification for Boron-based NeutronAbsorbing Ma-
Neutron Attenuation Measurements
G1 Practice for Preparing, Cleaning, and Evaluating Corro-
sion Test Specimens
This guide is under the jurisdiction ofASTM Committee C26 on Nuclear Fuel
G4 Guide for Conducting Corrosion Tests in Field Applica-
Cycle and is the direct responsibility of Subcommittee C26.03 on NeutronAbsorber
Materials Specifications. tions
Current edition approved July 1, 2020. Published July 2020. Originally approved
G15 Terminology Relating to Corrosion and Corrosion Test-
in 1991. Last previous edition approved in 2020 as C1187 – 20. DOI: 10.1520/ 3
ing (Withdrawn 2010)
C1187-20A.
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
Standards volume information, refer to the standard’s Document Summary page on The last approved version of this historical standard is referenced on
the ASTM website. www.astm.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
C1187 − 20a
G16 Guide for Applying Statistics to Analysis of Corrosion 4. Significance and Use
Data
4.1 The storage of nuclear fuel in high-density storage racks
G46 Guide for Examination and Evaluation of Pitting Cor-
isdependentuponthefunctionalityandintegrityofanabsorber
rosion
between the stored fuel assemblies to ensure that the reactivity
G69 Test Method for Measurement of Corrosion Potentials
of the storage configuration does not exceed the K-effective
of Aluminum Alloys
allowed by applicable regulations. A confirmation test may be
requiredtoverifythefunctionalityandintegrityoftheabsorber
3. Terminology
within the racks. If establishing a surveillance program for
3.1 Definitions:
newly installed or existing absorber material in fuel racks, the
3.1.1 For definitions of terms used in this guide, refer to
following methods are suggested: (a) coupon monitoring
Terminology C859.
program (if coupons are available), (b) in-situ neutron attenu-
3.2 Definitions of Terms Specific to This Standard:
ation test, and (c) other applicable in-situ tests such as visual
3.2.1 absorber, n—a boron-based neutron-absorbing mate-
inspection or drag test.
rial system.
4.2 This guide provides guidance for establishing and con-
3.2.2 areal density, n—for neutron absorber materials with
ducting a surveillance program for monitoring the ongoing
flat parallel surfaces, the mass of boron-10 per unit area of a
functionality and integrity of the absorbers.
sheet, which is equivalent to the mass of boron-10 per unit
volume in the material multiplied by the thickness of the
5. Characteristics to Be Monitored
material in which that isotope is contained.
3.2.3 confirmation tests, n—tests that may be necessary to 5.1 The primary function of the absorber is to provide
confirmthecontinuedfunctionalityandintegrityoftheneutron sufficient absorption cross section for thermal neutrons
absorber. throughout the relatively high (neutron) flux region between
the active zones of adjacent fuel assemblies. The most impor-
3.2.4 degradation, n—a change in a material property that
tant characteristic to be monitored is the ability of the absorber
lessens the original design functionality.
to continuously and effectively remove thermal neutrons. This
3.2.5 high-density storage, n—the close-packing of fuel to
characteristic may vary over time after exposure to the heat,
theextentthatabsorbersarerequiredforneutronfluxreduction
radiation, water chemistry, and mechanical forces experienced
to assure adequate sub-criticality margin.
by the racks from the storage of nuclear fuel or natural
3.2.6 in-situ neutron attenuation test, n—a qualitative or
phenomena, or both.
quantitativetestusinganeutronsourcefordeterminingneutron
5.1.1 Absorbers should be monitored for verification of
absorbing functionalities.
adequate neutron absorbing functionality by periodic neutron
3.2.7 in-situ test, n—remote characterization of absorber
attenuationtestsofremovablesurveillancespecimensorin-situ
material in the storage racks.
neutron attenuation tests, or both.
3.2.8 irradiation (flux), n—the incidence of neutron and
5.1.2 Absorbers characterization should include consider-
gamma radiation from fuel assemblies on materials in a
ation of radiation damage or other types of deterioration that
water-filled fuel pool.
may reduce the physical integrity or functionality of the
absorber below the predetermined limits for the design service
3.2.9 neutron attenuation test, n—for neutron absorber
life of the racks (see 8.3).
materials, a process in which a material is placed in a thermal
neutron beam, and the number of neutrons transmitted through
the material in a specified period of time is counted. The 6. Surveillance Specimens
neutron count can be converted to areal density by performing
6.1 Whereverpossible,thedesignofsurveillancespecimens
the same test on a series of appropriate calibration standards
should be in accordance with the requirements of ASTM
and comparing the results. This definition is applicable to
standards for the specific properties of interest to be measured.
in-situ testing of neutron absorber materials or the testing of
The size and configuration of certain specimens should be
surveillance coupons.
represen
...

This document is not an ASTM standard and is intended only to provide the user of an ASTM 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.
Designation: C1187 − 20 C1187 − 20a
Standard Guide for
Establishing Surveillance Test Program for Boron-based
Neutron Absorbing Material Systems for Use in Nuclear Fuel
Storage Racks in Pool Environment
This standard is issued under the fixed designation C1187; 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
1.1 This guide provides guidance for establishing a surveillance test program to monitor the performance of boron-based
neutron absorbing material systems (absorbers) necessary to maintain sub-criticality in nuclear fuel storage racks in a pool
environment. The practices presented in this guide, when implemented, will provide a comprehensive surveillance test program
to verify the functionality and integrity of the neutron absorbing material within the storage racks. The performance of a
surveillance test program provides added assurance of the safe and effective operation of a high-density storage facility for nuclear
fuel. There are several different techniques for surveillance testing of boron-based neutron absorbing materials. This guide focuses
on coupon monitoring and in-situ testing.
1.2 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.
1.3 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.
2. Referenced Documents
2.1 ASTM Standards:
C859 Terminology Relating to Nuclear Materials
C992 Specification for Boron-based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in Pool
Environment
C1068 Guide for Qualification of Measurement Methods by a Laboratory Within the Nuclear Industry
D412 Test Methods for Vulcanized Rubber and Thermoplastic Elastomers—Tension
D430 Test Methods for Rubber Deterioration—Dynamic Fatigue
D518 Test Method for Rubber Deterioration—Surface Cracking (Withdrawn 2007)
D813 Test Method for Rubber Deterioration—Crack Growth
D1415 Test Method for Rubber Property—International Hardness
D2240 Test Method for Rubber Property—Durometer Hardness
D3183 Practice for Rubber—Preparation of Pieces for Test Purposes from Products
D4483 Practice for Evaluating Precision for Test Method Standards in the Rubber and Carbon Black Manufacturing Industries
E6 Terminology Relating to Methods of Mechanical Testing
E8/E8M Test Methods for Tension Testing of Metallic Materials
E45 Test Methods for Determining the Inclusion Content of Steel
E74 Practices for Calibration and Verification for Force-Measuring Instruments
E290 Test Methods for Bend Testing of Material for Ductility
This guide is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.03 on Neutron Absorber
Materials Specifications.
Current edition approved Jan. 1, 2020July 1, 2020. Published February 2020July 2020. Originally approved in 1991. Last previous edition approved in 20152020 as
C1187 – 15.C1187 – 20. DOI: 10.1520/C1187-20.10.1520/C1187-20A.
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
The last approved version of this historical standard is referenced on www.astm.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
C1187 − 20a
E2971 Test Method for Determination of Effective Boron-10 Areal Density in Aluminum Neutron Absorbers using Neutron
Attenuation Measurements
G1 Practice for Preparing, Cleaning, and Evaluating Corrosion Test Specimens
G4 Guide for Conducting Corrosion Tests in Field Applications
G15 Terminology Relating to Corrosion and Corrosion Testing (Withdrawn 2010)
G16 Guide for Applying Statistics to Analysis of Corrosion Data
G46 Guide for Examination and Evaluation of Pitting Corrosion
G69 Test Method for Measurement of Corrosion Potentials of Aluminum Alloys
3. Terminology
3.1 Definitions:
3.1.1 For definitions of terms used in this guide, refer to Terminology C859.
3.2 Definitions of Terms Specific to This Standard:
3.2.1 absorber, n—a boron-based neutron-absorbing material system.
3.2.2 areal density, n—for neutron absorber materials with flat parallel surfaces, the mass of boron-10 per unit area of a sheet,
which is equivalent to the mass of boron-10 per unit volume of boron-10 in the material multiplied by the thickness of the material
in which that isotope is containedcontained.
3.2.3 confirmation tests, n—tests that may be necessary to confirm the continued functionality and integrity of the neutron
absorber.
3.2.4 degradation, n—a change in a material property that lessens the original design functionality.
3.2.5 high-density storage, n—the close-packing of fuel to the extent that absorbers are required for neutron flux reduction to
assure adequate sub-criticality margin.
3.2.6 in-situ neutron attenuation test, n—a qualitative or quantitative test using a neutron source for determining neutron
absorbing functionalities.
3.2.7 in-situ test, n—remote characterization of absorber material in the storage racks.
3.2.8 irradiation (flux), n—the incidence of neutron and gamma radiation from fuel assemblies on materials in a water-filled fuel
pool.
3.2.9 neutron attenuation test, n—for neutron absorber materials, a process in which a material is placed in a thermal neutron
beam, and the number of neutrons transmitted through the material in a specified period of time is counted. The neutron count can
be converted to areal density by performing the same test on a series of appropriate calibration standards and comparing the results.
This definition is applicable to in-situ testing of neutron absorber materials or the testing of surveillance coupons.
3.2.10 sample, n—one or more specimens of the absorber selected by some predetermined sampling process.
3.2.11 service life, n—the period of time for which properties of the absorber are expected to remain in compliance within the
design specifications.
3.2.12 specimen, n—an individual full-size piece of the absorber or any portion thereof selected and prepared as necessary for
test purposes.
4. Significance and Use
4.1 The storage of nuclear fuel in high-density storage racks is dependent upon the functionality and integrity of an absorber
between the stored fuel assemblies to ensure that the reactivity of the storage configuration does not exceed the K-effective allowed
by applicable regulations. A confirmation test may be required to verify the functionality and integrity of the absorber within the
racks. If establishing a surveillance program for newly installed or existing absorber material in fuel racks, the following methods
are suggested: (a) coupon monitoring program (if coupons are available), (b) in-situ neutron attenuation test, and (c) other
applicable in-situ tests such as visual inspection or drag test.
4.2 This guide provides guidance for establishing and conducting a surveillance program for monitoring the ongoing
functionality and integrity of the absorbers.
5. Characteristics to Be Monitored
5.1 The primary function of the absorber is to provide sufficient absorption cross section for thermal neutrons throughout the
relatively high (neutron) flux region between the active zones of adjacent fuel assemblies. The most important characteristic to be
monitored is the ability of the absorber to continuously and effectively remove thermal neutrons. This characteristic may vary over
time after exposure to the heat, radiation, water chemistry, and mechanical forces experienced by the racks from the storage of
nuclear fuel or natural phenomena, or both.
Pierce, T. B. “Some Uses of Neutrons From Non-reactor Sources for the Examination of Metals and Allied Materials.” IAEA-SM-159/17 pp. 49–61.Pierce, T. B., “Some
Uses of Neutrons From Non-reactor Sources for the Examination of Metals and Allied Materials,” IAEA-SM-159/17, pp. 49–61.
C1187 − 20a
5.1.1 Absorbers sho
...