ASTM E2216-02(2013)
(Guide)Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning
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.
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Standards Content (Sample)
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Designation: E2216 − 02 (Reapproved 2013)
Standard Guide for
Evaluating Disposal Options for Concrete from Nuclear
1
Facility Decommissioning
This standard is issued under the fixed designation E2216; 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.
INTRODUCTION
Numerous nuclear facilities containing large amounts of concrete are scheduled for decontamina-
tion and decommissioning over the next several decades. Much of this concrete is either not
contaminated or only lightly contaminated on or near the surface. However, since concrete is slightly
porous, it has the potential to be contaminated volumetrically. Volumetric contamination is more
difficult to measure than surface contamination, and currently there are no release guidelines for
volumetrically contaminated concrete.As a result, large volumes of concrete are often disposed of as
radioactive waste at a large cost.
Under certain conditions, the depth or amount of contamination may be limited such that a case can
be made for concrete release for other purposes outside of regulatory control. These cases are likely
to be ones where the radioactive contamination is shallow and is limited to a depth that can be
removed by scabbling (removal of the concrete surface), or where the depth can be estimated based
on the history and condition of the concrete. In addition to surface contaminated concrete, some
facilities contain activated concrete where the depths of contamination vary. This type of concrete
should be handled on a case-by-case basis.Accurate measurements of the radiation source are difficult
for activated concrete, because the activated portions of the embedded metal or concrete are partially
shielded by the concrete that lies between the source and the measuring device. Care must be taken
to measure radiation levels of activated concrete accurately, so actual radiation levels are documented
and used when applying release criteria.
This standard guide applies to nonrubbelized concrete that is still in place with a defined geometry
and known history where the depth of contamination can be measured or estimated based on its
history. It is not practical to measure radiation levels of concrete rubble. The process outlined here
starts with characterizing the concrete in place, then evaluating the dose to the public and cost of
various disposal options.
1. Scope cost and select the best disposal option. These data, which
establish a technical basis to apply to release the concrete, can
1.1 This standard guide defines the process for developing a
be used in several ways: (1) to show that the release meets
strategy for dispositioning concrete from nuclear facility de-
existing release criteria, (2) to establish a basis to request
commissioning. It outlines a 10-step method to evaluate
release of the concrete on a case-by-case basis, (3) to develop
disposal options for radioactively contaminated concrete. One
a basis for establishing release criteria where none exists.
of the steps is to complete a detailed analysis of the cost and
dose to nonradiation workers (the public); the methodology
1.2 This standard guide is based on the “Protocol for
and supporting data to perform this analysis are detailed in the
Development of Authorized Release Limits for Concrete at
2
appendices.The resulting data can be used to balance dose and
U.S.DepartmentofEnergySites,”(1) fromwhichtheanalysis
methodology and supporting data are taken.
1.3 Guide E1760 provides a general process for release of
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
materials containing residual amounts of radioactivity. In
Technology and Applications and is the direct responsibility of Subcommittee
E10.03 on Radiological Protection for Decontamination and Decommissioning of
Nuclear Facilities and Components.
Current edition approved Jan. 1, 2013. Published January 2013. Originally
2
approvedin2002.Lastpreviouseditionapprovedin2008asE2216–02(2008).DOI: The boldface numbers in parentheses refer to a list of references at the end of
10.1520/E2216-02R13. this standard.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
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E2216 − 02 (2013)
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addition, Guide E1278 provides a general process for analyz- 2.5 DOE Standards:
ing radioactive pathways. This standard guide is intended for DOE G 441.1–1B Radiation Protection Programs Guide,
use in conjunction with Guides E1760 and E1278, and pro- Order 5400.5 Radiation Protection of the Public and the
vides a
...
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