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ASTM C992-06

(Specification)

Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks

Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks

ABSTRACT
This specification defines essential criteria for all material combinations in boron-based neutron-absorbing material systems used for nuclear spent fuel storage racks in nuclear light water reactors, spent-fuel assemblies, or disassembled components. The boron-based neutron absorbing materials normally consist of metallic boron or a boron-containing boron compound supported by a matrix of aluminum, steel, or other materials. Material systems covered in this specification should always be capable of maintaining a B10 areal density that can support the required subcriticality depending on the design specification for service life.
SCOPE
1.1 This specification defines criteria for boron-based neutron absorbing material systems used in racks in a pool environment for storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components to maintain sub-criticality in the storage rack system.
1.2 Boron-based neutron absorbing material systems normally consist of metallic boron or a chemical compound containing boron (for example, boron carbide, B4C) supported by a matrix of aluminum, steel, or other materials.
1.3 In a boron-based absorber, neutron absorption occurs primarily by the boron-10 isotope that is present in natural boron to the extent of 18.3 0.2% by weight (depending upon the geological origin of the boron). Boron, enriched in boron-10 could also be used.
1.4 The materials systems described herein shall be functional - that is always be capable to maintain a B10 areal density such that subcriticality Keff 0.95 or Keff 0.98 or Keff 1.0 depending on the design specification for the service life (approximately 40 years) in the operating environment of a nuclear spent fuel pool.
1.5 A number of acceptable boron-based absorbing materials combinations are currently available while others are being developed for use in the future. This specification defines criteria essential and applicable to all materials combinations and identifies parameters a buyer should specify to satisfy a unique or particular requirement.
1.6 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or requirements for health and safety. Observance of this specification does not relieve the user of the obligation to conform to all applicable international, national, and local regulations.

General Information

Status
Historical
Publication Date
14-Feb-2006
ICS
27.120.01 - Nuclear energy in general
Technical Committee
C26 - Nuclear Fuel Cycle
Drafting Committee
C26.03 - Neutron Absorber Materials Specifications
Current Stage
Ref Project

Relations

Replaces
ASTM C992-89(1997) - Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks
Effective Date
15-Feb-2006
Replaced By
ASTM C992-11 - Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks
Effective Date
01-Feb-2011
Referred By
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
Effective Date
15-Feb-2006

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ASTM C992-06 - Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage RacksASTM C992-06 - Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks
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ASTM C992-06 - Standard Specification for Boron-Based Neutron Absorbing Material Systems for Use in Nuclear Spent Fuel Storage Racks
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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
Designation: C992 – 06
Standard Specification for
Boron-Based Neutron Absorbing Material Systems for Use
1
in Nuclear Spent Fuel Storage Racks
This standard is issued under the fixed designation C992; 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 2. Referenced Documents
2
1.1 This specification defines criteria for boron-based neu- 2.1 ASTM Standards:
tron absorbing material systems used in racks in a pool A240/A240M Specification for Chromium and Chromium-
environment for storage of nuclear light water reactor (LWR) Nickel Stainless Steel Plate, Sheet, and Strip for Pressure
spent-fuel assemblies or disassembled components to maintain Vessels and for General Applications
sub-criticality in the storage rack system. B209 Specification for Aluminum and Aluminum-Alloy
1.2 Boron-based neutron absorbing material systems nor- Sheet and Plate
mally consist of metallic boron or a chemical compound C750 Specification for Nuclear-Grade Boron Carbide Pow-
containing boron (for example, boron carbide, B C) supported der
4
by a matrix of aluminum, steel, or other materials. C859 Terminology Relating to Nuclear Materials
1.3 In a boron-based absorber, neutron absorption occurs E105 Practice for Probability Sampling Of Materials
primarily by the boron-10 isotope that is present in natural ASTM Dictionary of Engineering Science and Technology
3
boron to the extent of 18.3 6 0.2% by weight (depending upon 2.2 ANSI Standards:
the geological origin of the boron). Boron, enriched in ANSI 45.2.2 Packaging, Shipping, Receiving, Storage and
boron-10 could also be used. Handling of Items for Nuclear Power Plants
1.4 The materials systems described herein shall be func- ANSI-ASME NQA-1 Quality Assurance Requirements for
tional – that is always be capable to maintain a B10 areal Nuclear Facility Application
4
density such that subcriticality Keff <0.95 or Keff <0.98 or 2.3 U. S. Government Documents:
Keff<1.0dependingonthedesignspecificationfortheservice Title 10, CFR, Energy Part 50 (10CFR50) Licensing of
life (approximately 40 years) in the operating environment of Production and Utilization Facilities
a nuclear spent fuel pool. Title 10, CFR, Energy Part 72 (10CFR72) Licensing Re-
1.5 A number of acceptable boron-based absorbing materi- quirements for the Storage of Spent Fuel in an Indepen-
als combinations are currently available while others are being dent Spent Fuel Storage Installation (ISFSI)
developed for use in the future. This specification defines
3. Terminology
criteria essential and applicable to all materials combinations
3.1 Definitions of Terms Specific to This Standard:
and identifies parameters a buyer should specify to satisfy a
unique or particular requirement. 3.1.1 Terms shall be defined in accordance with Terminol-
ogy C859 or theASTM Dictionary of Engineering Science and
1.6 The scope of this specification does not comprehen-
sively cover all provisions for preventing criticality accidents Technology, except as defined as follows:
3.1.2 accelerated testing—a procedure for investigating the
or requirements for health and safety. Observance of this
specification does not relieve the user of the obligation to potential for long-term changes in physical properties or
chemical composition of a material important to safety, caused
conform to all applicable international, national, and local
regulations.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
1
This specification is under the jurisdiction of ASTM Committee C26 on Standards volume information, refer to the standard’s Document Summary page on
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.03 on the ASTM website.
3
Neutron Absorber Materials Specifications. Available from theAmerican National Standards Institute, 11W. 42nd St., 13th
Current edition approved Feb. 15, 2006. Published March 2006. Originally Floor, New York, NY 10036.
4
approvedin1983.Lastpreviouseditionapprovedin1997asC992 – 89(1997).DOI: Available from Superintendent of Documents, U. S. Government Printing
10.1520/C0992-06. Office, Washington, DC 20402.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
C992 – 06
by a system operating parameter such as temperature chemical 4.2.4 Applicable tolerances for each dimension or property,
environment or radiation. The procedure uses a value of the including minimum boron-10 areal density.
identified pa
...

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13  
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17  
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Standard Specification for Boron-based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in Pool Environment

ABSTRACT
This specification defines essential criteria for all material combinations in boron-based neutron-absorbing material systems used for nuclear spent fuel storage racks in nuclear light water reactors, spent-fuel assemblies, or disassembled components. The boron-based neutron absorbing materials normally consist of metallic boron or a boron-containing boron compound supported by a matrix of aluminum, steel, or other materials. Material systems covered in this specification should always be capable of maintaining a B10 areal density that can support the required subcriticality depending on the design specification for service life.
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5.1 Information is provided in this document and other referenced documents to assist the licensee and the licensor in analyzing the materials aspects of performance of SNF and DCSS components during extended storage. The effects of the service conditions of the first licensing period are reviewed in the license renewal process. These service conditions are highlighted and discussed in Annex A1 as factors that affect materials performance in an ISFSI. Emphasis is on the effects of time, temperature, radiation, and the environment on the condition of the SNF and the performance of components of ISFSI storage systems.  
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1.5 No units are used in this statistical analysis.  
1.6 This guide does not involve the use of materials, operations, or equipment and does not address any risk associated.  
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SIGNIFICANCE AND USE
4.1 A laboratory quality assurance program is an essential program for laboratories within the nuclear industry. Guide C1009 provides guidance for establishing a quality assurance program for an analytical laboratory within the nuclear industry. This guide deals with the control of measurements aspect of the laboratory quality assurance program. Fig. 1 shows the relationship of measurement control with other essential aspects of a laboratory quality assurance program.
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1.1 This guide provides guidance for establishing and maintaining a measurement system quality control program. Guidance is provided for general program considerations, preparation of quality control samples, analysis of quality control samples, quality control data analysis, analyst qualification, measurement system calibration, measurement method qualification, and measurement system maintenance.  
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5  
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11  
Measurement System Maintenance  
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Standard Guide for Establishing and Maintaining a Quality Assurance Program for Analytical Laboratories Within the Nuclear Industry

SIGNIFICANCE AND USE
4.1 The mission of an analytical laboratory is to provide quality analyses on nuclear fuel cycle materials. An analytical laboratory QA program is comprised of planned and systematic actions needed to provide confidence that this mission is conducted in an acceptable and consistent manner.  
4.2 The analytical laboratories involved in the analysis of nuclear fuel cycle materials are required to implement a documented QA program. Regulatory agencies may mandate some form of control requirements for all or a part of a laboratory's operation. A documented QA program is also necessary for those laboratory operations required to comply with ASME NQA-1 or ISO/IEC 17025, or the requirements of many accreditation bodies. Even when not mandated, laboratory QA programs should be established as a sound and scientific technical practice. This guide provides guidance for establishing and maintaining a QA program to control those analytical operations vital to ensuring the quality of chemical analyses.  
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FIG. 1 Essential Elements of Analytical Laboratory Quality Assurance System  
4.5 Althoug...
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4.2 It is not practical to impose all the requirements of this practice on certain specific items that require only a small quantity of coating material. The licensee, consistent with his formal Quality Assurance Program, may accept affidavits of compliance or certification attesting to the quality of a shop or field coating for such items. If required by licensing commitment; safety-related coatings that are not qualified or for which the quantification basis is indeterminate as defined in Guide D5144, shall be identified, quantified, and documented.  
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1.2 This standard meets the requirements of ANSI N101.4 while also recognizing advancements in technology and industry practices since transfer to ASTM responsibility for updating, rewriting, and issuing replacement standards to ANSI N101.4.  
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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    18 pages
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ASTM
ASTM E2216-02(2020)(Guide)
Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning

SIGNIFICANCE AND USE
4.1 This standard guide applies to concrete that is still in place with a defined geometry and known, documented history.  
4.2 It is not intended for use on concrete that has already been rubbelized where it is difficult to measure the radiation levels and not easy to remove surface contamination to reduce radiation levels after concrete has been rubbelized.  
4.3 This standard guide applies to surface or volumetrically contaminated concrete, where the depth of contamination can be measured or estimated based on the history of the concrete.  
4.4 This standard guide does not apply to the reinforcement bar (rebar) found in concrete. Although most concrete contains rebar, it is generally removed before the concrete is dispositioned. In addition, rebar may be activated, and is covered under procedures for reuse of scrap metal.  
4.5 General unit-dose and unit-cost data to support the calculations is provided in the appendices of this standard guide. However, if site-specific data is available, it should be used instead of the general information provided here.  
4.6 This standard guide helps determine estimated doses to the public during disposal of concrete and to future residents of disposal areas. It does not include dose to radiation workers already involved in a radiation control program. It is assumed that the dose to radiation workers is already tracked and kept within acceptable levels through a radiation control program. The cost and dose to radiation workers could be added in to find an overall cost and dose for each option.
SCOPE
1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, (2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists.  
1.2 This standard guide is based on the “Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites,” (1)2 from which the analysis methodology and supporting data are taken.  
1.3 Guide E1760 provides a general process for release of materials containing residual amounts of radioactivity. In addition, Guide E1278 provides a general process for analyzing radioactive pathways. This standard guide is intended for use in conjunction with Guides E1760 and E1278, and provides a more detailed approach for the release of concrete.  
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 C992-20a(Specification)
Standard Specification for Boron-based Neutron Absorbing Material Systems for Use in Nuclear Fuel Storage Racks in Pool Environment

ABSTRACT
This specification defines essential criteria for all material combinations in boron-based neutron-absorbing material systems used for nuclear spent fuel storage racks in nuclear light water reactors, spent-fuel assemblies, or disassembled components. The boron-based neutron absorbing materials normally consist of metallic boron or a boron-containing boron compound supported by a matrix of aluminum, steel, or other materials. Material systems covered in this specification should always be capable of maintaining a B10 areal density that can support the required subcriticality depending on the design specification for service life.
SCOPE
1.1 This specification defines criteria for boron-based neutron absorbing material systems used in racks in a pool environment for storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components to maintain sub-criticality in the storage rack system.  
1.2 Boron-based neutron absorbing material systems normally consist of metallic boron or a chemical compound containing boron (for example, boron carbide, B4C) supported by a matrix of aluminum, steel, or other materials.  
1.3 In a boron-based absorber, neutron absorption occurs primarily by the boron-10 isotope that is present in natural boron to the extent of 18.3 ± 0.2 % by weight (depending upon the geological origin of the boron). Boron enriched in boron-10 could also be used.  
1.4 The materials systems described herein shall be functional (that is, always be capable to maintain a boron-10 areal density such that subcriticality is maintained depending on the design specification for the service life in the operating environment of a nuclear spent fuel pool).  
1.5 Observance of this specification does not relieve the user of the obligation to conform to all applicable international, national, and local regulations.  
1.6 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.  
1.7 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.

  • Technical specification
    4 pages
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  • Technical specification
    4 pages
    English language
    sale 15% off