ASTM C1751-11
(Guide)Standard Guide for Sampling Radioactive Tank Waste
Standard Guide for Sampling Radioactive Tank Waste
SIGNIFICANCE AND USE
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.
Many high-level wastes have been treated to remove strontium (Sr) or cesium (Cs), or both, underwent liquid volume reductions through 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 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.
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 assumption that the tank headspace is adequately ventilated during sampling.
TABLE 1 High-Level Waste Tank Sampling Methods TechniqueMaterial TypeNotes SolidSlurryLiquid HAST in-tank
needle orifice
X
Orifice as part of Reverse-Flow
Diverter (RFD)
B...
SCOPE
1.1 This guide addresses techniques used to obtain grab 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). 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.
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Designation: C1751 − 11
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 3.2.2 pH modified, n—a description of a solution where the
pH is adjusted with either an acid or base material to achieve
1.1 This guide addresses techniques used to obtain grab
a desired pH level to minimize tank corrosion.
samples from tanks containing high-level radioactive waste
3.2.3 soft sludge, n—a sludge with a low viscosity where
created during the reprocessing of spent nuclear fuels. Guid-
minimal sampling device pressure could be used to penetrate
ance on selecting appropriate sampling devices for waste
the sludge layer.
covered by the Resource Conservation and Recovery Act
(RCRA) is also provided by the United States Environmental
3.2.4 sparge, n—a process of delivering a chemically inert
2
Protection Agency (EPA) (1). Vapor sampling of the head-
gas through fluids to displace materials for the purpose of
space is not included in this guide because it does not
mixing.
significantly affect slurry retrieval, pipeline transport,
3.3 Acronyms:
plugging, or mixing.
3.3.1 EREE—Extended Reach End-Effector
1.2 The values stated in inch-pound units are to be regarded
3.3.2 HAST—Highly-Active Storage Tanks
as standard. No other units of measurement are included in this
3.3.3 LDUAs—Light-Duty Utility Arms
standard.
3.3.4 NPH—Normal Paraffin Hydrocarbons
1.3 This standard does not purport to address all of the
3.3.5 ORNL—Oak Ridge National Laboratory
safety concerns, if any, associated with its use. It is the
responsibility of the user of this standard to establish appro-
3.3.6 PTFE—Polytetrafluoroethylene
priate safety and health practices and determine the applica-
3.3.7 PVC—Polyvinyl Chloride
bility of regulatory limitations prior to use.
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-
lenges. Generally, high-level waste is stored in tanks with
3. Terminology
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.
3.2 Definitions of Terms Specific to This Standard:
The quantity of sample that can be obtained and transported is
3.2.1 forced evaporation, n—intentional concentration of a
small due to the hazardous nature of the samples as well as
waste solution using heat or vacuum, or both, primarily to
their high radiation dose.
remove water or other solvents.
4.2 Many high-level wastes have been treated to remove
strontium (Sr) or cesium (Cs), or both, underwent liquid
1 volumereductionsthroughforcedevaporationorhavebeenpH
This practice is under the jurisdiction of ASTM Committee C26 on Nuclear
Fuel Cycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel
modified, or both, to decrease corrosion of the tanks. These
and High Level Waste.
processes, as well as waste streams added from multiple
Current edition approved June 1, 2011. Published July 2011. DOI: 10.1520/
process plant operations, often resulted in precipitation, and
C1751-11.
2
produced multiphase wastes that are heterogeneous. Evapora-
The boldface numbers in parentheses refer to a list of references at the end of
this standard.
tion of water from waste with significant dissolved salts
3
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
concentrations has occurred in some tanks due to the high heat
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
load associated with the high-level waste and by intentional
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. evaporative processing, resulting in the formation of a saltcake
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
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C1751 − 11
or crusts, or both. Organic layers exist in some waste tanks, the high-level waste was added. The HAST system uses a
creating additional heterogeneity in the wastes. needle orifice as part of a Reverse-Flow Diverter (RFD) to
obtain samples. The needle orifices are
...
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