ASTM C1751-21

Standard Guide for Sampling Radioactive Tank Waste

SIGNIFICANCE AND USE
4.1 Obtaining samples of high-level waste created during the reprocessing of spent nuclear fuels presents unique challenges. Generally, high-level waste is stored in tanks with limited access to decrease the potential for radiation exposure to personnel. Samples must be obtained remotely because of the high radiation dose from the bulk material and the samples, samples require shielding for handling, transport, and storage. The quantity of sample that can be obtained and transported is small due to the hazardous nature of the samples as well as their high radiation dose.  
4.2 Many high-level wastes have been treated to remove strontium (Sr) or cesium (Cs), or both, have undergone liquid volume reductions through pumping and forced evaporation or have been pH modified, or both, to decrease corrosion of the tanks. These processes, as well as waste streams added from multiple process plant operations, often resulted in precipitation, and produced multiphase wastes that are heterogeneous. Evaporation of water from waste with significant dissolved salts concentrations has occurred in some tanks due to the high heat load associated with the high-level waste and by pumping and intentional evaporative processing, resulting in the formation of a saltcake or crusts, or both. Organic layers exist in some waste tanks, creating additional heterogeneity in the wastes.  
4.3 Many of the sampling systems have limitations including the ability to sample varying depths in the tank and the depth of sampling. Sampling in Hanford tanks is constrained by riser diameter, riser location and riser availability.  
4.4 Due to these extraordinary challenges, substantial effort in research and development has been expended to develop techniques to provide grab samples of the contents of the high-level waste tanks. A summary of the primary techniques used to obtain samples from high-level waste tanks is provided in Table 1. These techniques will be summarized in this guideline with the assum...
SCOPE
1.1 This guide addresses techniques used to obtain samples from tanks containing high-level radioactive waste created during the reprocessing of spent nuclear fuels. Guidance on selecting appropriate sampling devices for waste covered by the Resource Conservation and Recovery Act (RCRA) is also provided by the United States Environmental Protection Agency (EPA) (1).2 Vapor sampling of the head-space is not included in this guide because it does not significantly affect slurry retrieval, pipeline transport, plugging, or mixing.  
1.2 The values stated in inch-pound units are to be regarded as standard. No other units of measurement are included in this 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 and health 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.

General Information

• Status: Published
• Publication Date: 31-Dec-2020
• ICS: 13.030.30 - Special wastes
• Technical Committee: C26 - Nuclear Fuel Cycle
• Drafting Committee: C26.13 - Spent Fuel and High Level Waste

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: C1751 − 21
Standard Guide for
1
Sampling Radioactive Tank Waste
This standard is issued under the fixed designation C1751; 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 3.2 Definitions of Terms Specific to This Standard:
3.2.1 forced evaporation, n—intentional concentration of a
1.1 This guide addresses techniques used to obtain samples
waste solution using heat or vacuum, or both, primarily to
from tanks containing high-level radioactive waste created
remove water or other solvents.
during the reprocessing of spent nuclear fuels. Guidance on
selecting appropriate sampling devices for waste covered by 3.2.2 pH modified, n—a description of a solution where the
the Resource Conservation and Recovery Act (RCRA) is also pH is adjusted with either an acid or base material to achieve
provided by the United States Environmental Protection a desired pH level to minimize tank corrosion.
2
Agency (EPA) (1). Vapor sampling of the head-space is not
3.2.3 soft sludge, n—a sludge with a low viscosity where
included in this guide because it does not significantly affect
minimal sampling device pressure could be used to penetrate
slurry retrieval, pipeline transport, plugging, or mixing.
the sludge layer.
1.2 The values stated in inch-pound units are to be regarded
3.2.4 sparge, n—a process of delivering a chemically inert
as standard. No other units of measurement are included in this
gas through fluids to displace materials for the purpose of
standard.
mixing.
1.3 This standard does not purport to address all of the
3.3 Acronyms:
safety concerns, if any, associated with its use. It is the
3.3.1 EREE—Extended Reach End-Effector
responsibility of the user of this standard to establish appro-
3.3.2 HAST—Highly-Active Storage Tanks
priate safety, health, and environmental practices and deter-
mine the applicability of regulatory limitations prior to use. 3.3.3 LDUAs—Light-Duty Utility Arms
1.4 This international standard was developed in accor-
3.3.4 NPH—Normal Paraffin Hydrocarbons
dance with internationally recognized principles on standard-
3.3.5 ORNL—Oak Ridge National Laboratory
ization established in the Decision on Principles for the
3.3.6 PTFE—Polytetrafluoroethylene
Development of International Standards, Guides and Recom-
mendations issued by the World Trade Organization Technical
3.3.7 PVC—Polyvinyl Chloride
Barriers to Trade (TBT) Committee.
3.3.8 RFD—Reverse-Flow Diverter
2. Referenced Documents
4. Significance and Use
3
2.1 ASTM Standards:
4.1 Obtaining samples of high-level waste created during
D1129 Terminology Relating to Water
the reprocessing of spent nuclear fuels presents unique chal-
3. Terminology
lenges. Generally, high-level waste is stored in tanks with
limited access to decrease the potential for radiation exposure
3.1 Definitions—For definitions of terms used in this
to personnel. Samples must be obtained remotely because of
method, refer to Terminology D1129.
the high radiation dose from the bulk material and the samples,
samples require shielding for handling, transport, and storage.
1
This guide is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel
The quantity of sample that can be obtained and transported is
Cycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel and
small due to the hazardous nature of the samples as well as
High Level Waste.
their high radiation dose.
Current edition approved Jan. 1, 2021. Published March 2021. Originally
approved in 2011. Last previous edition approved in 2020 as C1751 – 20. DOI:
4.2 Many high-level wastes have been treated to remove
10.1520/C1751-21.
2
strontium (Sr) or cesium (Cs), or both, have undergone liquid
The boldface numbers in parentheses refer to a list of references at the end of
this standard.
volume reductions through pumping and forced evaporation or
3
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
have been pH modified, or both, to decrease corrosion of the
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
tanks. These processes, as well as waste streams added from
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. multiple process plant operations, often resulted in
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

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...

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: C1751 − 20 C1751 − 21
Standard Guide for
1
Sampling Radioactive Tank Waste
This standard is issued under the fixed designation C1751; 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 addresses techniques used to obtain samples from tanks containing high-level radioactive waste created during the
reprocessing of spent nuclear fuels. Guidance on selecting appropriate sampling devices for waste covered by the Resource
2
Conservation and Recovery Act (RCRA) is also provided by the United States Environmental Protection Agency (EPA) (1). Vapor
sampling of the head-space is not included in this guide because it does not significantly affect slurry retrieval, pipeline transport,
plugging, or mixing.
1.2 The values stated in inch-pound units are to be regarded as standard. No other units of measurement are included in this
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 and health 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.
2. Referenced Documents
3
2.1 ASTM Standards:
D1129 Terminology Relating to Water
3. Terminology
3.1 Definitions—For definitions of terms used in this method, refer to Terminology D1129.
3.2 Definitions of Terms Specific to This Standard:
3.2.1 forced evaporation, n—intentional concentration of a waste solution using heat or vacuum, or both, primarily to remove
water or other solvents.
1
This practiceguide is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel and
High Level Waste.
Current edition approved Jan. 1, 2020Jan. 1, 2021. Published January 2020March 2021. Originally approved in 2011. Last previous edition approved in 20112020 as
C1751 – 11.C1751 – 20. DOI: 10.1520/C1751-20.10.1520/C1751-21.
2
The boldface numbers in parentheses refer to a list of references at the end of this standard.
3
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.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C1751 − 21
3.2.2 pH modified, n—a description of a solution where the pH is adjusted with either an acid or base material to achieve a desired
pH level to minimize tank corrosion.
3.2.3 soft sludge, n—a sludge with a low viscosity where minimal sampling device pressure could be used to penetrate the sludge
layer.
3.2.4 sparge, n—a process of delivering a chemically inert gas through fluids to displace materials for the purpose of mixing.
3.3 Acronyms:
3.3.1 EREE—Extended Reach End-Effector
3.3.2 HAST—Highly-Active Storage Tanks
3.3.3 LDUAs—Light-Duty Utility Arms
3.3.4 NPH—Normal Paraffin Hydrocarbons
3.3.5 ORNL—Oak Ridge National Laboratory
3.3.6 PTFE—Polytetrafluoroethylene
3.3.7 PVC—Polyvinyl Chloride
3.3.8 RFD—Reverse-Flow Diverter
4. Significance and Use
4.1 Obtaining samples of high-level waste created during the reprocessing of spent nuclear fuels presents unique challenges.
Generally, high-level waste is stored in tanks with limited access to decrease the potential for radiation exposure to personnel.
Samples must be obtained remotely because of the high radiation dose from the bulk material and the samples;samples, samples
require shielding for handling, transport, and storage. The quantity of sample that can be obtained and transported is small due to
the hazardous nature of the samples as well as their high radiation dose.
4.2 Many high-level wastes have been treated to remove strontium (Sr) or cesium (Cs), or both, have undergone liquid volume
reductions through pumping and forced
...