Standard Guide for Characterization of Radioactive and/or Hazardous Wastes for Thermal Treatment (Withdrawn 2018)

SIGNIFICANCE AND USE
This guide identifies methods to determine the physical and chemical characteristics of a variety of hazardous and/or radioactive wastes including heavy metal contaminated wastes. These wastes can be in the physical form of sludges (wet or dry), spent waste water filter aids, waste water filter cakes, incinerator ashes (wet or dry), incinerator blowdown (wet or dry), asbestos, resins, zeolites, soils, unset or unsatisfactory cementitious waste forms in need of remediation, lead paint wastes, radioactively or non-radioactively contaminated asbestos, geologic mill tailings (also known as byproduct materials) and other naturally occurring or accelerator produced radioactive materials (NORM and NARM), etc. and combinations of the above. This guide may not be applicable to piping, duct work, rubble, debris waste or wastes containing these components.
This guide identifies the physical and chemical characteristics useful for developing high temperature thermal treatment methodologies for a variety of hazardous and/or radioactive process wastes and soils including heavy metal contaminated wastes. The waste characteristics can be used to (1) choose and develop the thermal treatment methodology, (2) determine if waste pretreatment is needed, (3) aid in development of thermal treatment process control, (4) develop surrogate waste formulations, (5) perform treatability studies, (6) determine processing regions (envelopes) of acceptable waste form composition, and/or (7) perform pilot scale testing with actual or surrogate waste, and/or (8) determine the composition and concentrations of off-gas species for regulatory compliance.
This guide identifies applicable test methods that can be used to measure the desired characteristics of the hazardous and/or radioactive wastes described in 4.1. The analyses discussed in this standard can be performed by a variety of techniques depending on equipment availability. For example, Gas Chromatograph Mass Spectrometry (GC/MS) can be us...
SCOPE
1.1 This guide identifies methods to determine the physical and chemical characteristics of radioactive and/or hazardous wastes before a waste is processed at high temperatures, for example, vitrification into a homogeneous glass ,glass-ceramic, or ceramic waste form. This includes waste forms produced by ex-situ vitrification (ESV), in-situ vitrification (ISV), slagging, plasma-arc, hot-isostatic pressing (HIP) and/or cold-pressing and sintering technologies. Note that this guide does not specifically address high temperature waste treatment by incineration but several of the analyses described in this guide may be useful diagnostic methods to determine incinerator off-gas composition and concentrations.
The characterization of the waste(s) recommended in this guide can be used to (1) choose and develop the appropriate thermal treatment methodology, (2) determine if waste pretreatment is needed prior to thermal treatment, (3) aid in development of thermal treatment process control, (4) develop surrogate waste formulations, (5) perform treatability studies, (6) determine processing regions (envelopes) of acceptable waste form composition, (7) perform pilot scale testing with actual or surrogate waste, and/or (8) determine the composition and concentrations of off-gas species for regulatory compliance.
The analyses discussed in this standard can be performed by a variety of techniques depending on equipment availability. For example, Gas Chromatograph Mass Spectrometry (GC/MS) can be used to measure the amount and type of off-gas species present. However, this standard assumes that such sophisticated equipment is unavailable for radioactive or hazardous waste service due to potential contamination of the equipment. The analyses recommended are, therefore, the simplest and least costly analyses that can be performed and still be considered adequate
1.2 This guide is applicable to radioactive and/or hazardous wastes i...

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Status
Withdrawn
Publication Date
31-Dec-2011
Current Stage
Ref Project

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ASTM C1571-03(2012) - Standard Guide for Characterization of Radioactive and/or Hazardous Wastes for Thermal Treatment (Withdrawn 2018)
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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: C1571 − 03 (Reapproved 2012)
Standard Guide for
Characterization of Radioactive and/or Hazardous Wastes
for Thermal Treatment
This standard is issued under the fixed designation C1571; 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 1.2 This guide is applicable to radioactive and/or hazardous
wastes including but not limited to, high-level wastes, low-
1.1 This guide identifies methods to determine the physical
level wastes, transuranic (TRU) wastes, hazardous wastes,
and chemical characteristics of radioactive and/or hazardous
mixed (hazardous and radioactive) wastes, heavy metal con-
wastes before a waste is processed at high temperatures, for
taminated wastes, and naturally occurring or accelerator pro-
example,vitrificationintoahomogeneousglass,glass-ceramic,
duced radioactive material (NARM or NORM) wastes. These
or ceramic waste form.This includes waste forms produced by
wastes can be in the physical form of wet sludges, dried
ex-situ vitrification (ESV), in-situ vitrification (ISV), slagging,
sludges, spent waste water filter aids, waste water filter cakes,
plasma-arc, hot-isostatic pressing (HIP) and/or cold-pressing
incinerator ashes (wet or dry), incinerator blowdown (wet or
and sintering technologies. Note that this guide does not
dry), wastewaters, asbestos, resins, zeolites, soils, unset or
specifically address high temperature waste treatment by in-
unsatisfactory cementitious wastes forms in need of
cineration but several of the analyses described in this guide
remediation, lead paint wastes, etc. and combinations of the
may be useful diagnostic methods to determine incinerator
above. This guide may not be applicable to piping, duct work,
off-gas composition and concentrations.
rubble, debris waste or wastes containing these components.
The characterization of the waste(s) recommended in this
1.3 This guide references applicable test methods that can
guide can be used to (1) choose and develop the appropriate
be used to characterize hazardous wastes, radioactive wastes,
thermal treatment methodology, (2) determine if waste pre-
and heavy metal contaminated process wastes, waste forms,
treatment is needed prior to thermal treatment, (3) aid in
NARM or NORM wastes, and soils.
development of thermal treatment process control, (4) develop
1.4 These test methods must be performed in accordance
surrogate waste formulations, (5) perform treatability studies,
with all quality assurance requirements for acceptance of the
(6) determine processing regions (envelopes) of acceptable
data.
waste form composition, (7) perform pilot scale testing with
1.5 This standard may involve hazardous materials,
actualorsurrogatewaste,and/or(8)determinethecomposition
operations, and equipment. This standard does not purport to
and concentrations of off-gas species for regulatory compli-
address all of the safety concerns, if any, associated with its
ance.
use. It is the responsibility of the user of this standard to
The analyses discussed in this standard can be performed by
establish appropriate safety and health practices and deter-
a variety of techniques depending on equipment availability.
mine the applicability of regulatory limitations prior to use.
For example, Gas Chromatograph Mass Spectrometry (GC/
MS) can be used to measure the amount and type of off-gas
2. Referenced Documents
species present. However, this standard assumes that such
2.1 ASTM Standards:
sophisticated equipment is unavailable for radioactive or haz-
C92 Test Methods for Sieve Analysis and Water Content of
ardous waste service due to potential contamination of the
Refractory Materials
equipment. The analyses recommended are, therefore, the
C146 Test Methods for Chemical Analysis of Glass Sand
simplest and least costly analyses that can be performed and
C162 Terminology of Glass and Glass Products
still be considered adequate
Highlevelwaste(HLW)isusedasagenerictermthatincludeshighlevelliquid
waste (HLLW) and high level radioactive waste (HRW).
1 3
This guide is under the jurisdiction ofASTM Committee C26 on Nuclear Fuel Low level waste (LLW) is used as a generic term that includes low level liquid
Cycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel and waste (LLLW), low level radioactive waste (LLRW) and low activity waste (LAW).
High Level Waste. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved Jan. 1, 2012. Published January 2012. Originally contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
approved in 2003. Last previous edition approved in 2003 as C1571–03. DOI: Standards volume information, refer to the standard’s Document Summary page on
10.1520/C1571-03R12. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
C1571 − 03 (2012)
C169 Test Methods for Chemical Analysis of Soda-Lime 3.1.4 debris waste—solid material exceeding a 60mm par-
and Borosilicate Glass ticle size that is intended for disposal and that is: a manufac-
C242 Terminology of Ceramic Whitewares and Related tured object; or plant or animal matter; or natural geologic
Products material.
C859 Terminology Relating to Nuclear Materials
3.1.5 devitrification—crystallization of glass. C162
C1109 Practice for Analysis of Aqueous Leachates from
3.1.6 drying—removal by evaporation, of uncombined wa-
Nuclear Waste Materials Using Inductively Coupled
ter or other volatile substances from a ceramic raw material or
Plasma-Atomic Emission Spectroscopy
product, usually expedited by low-temperature heating. C242
C1111 Test Method for Determining Elements in Waste
3.1.7 geologic mill tailings—common rock leftover from
StreamsbyInductivelyCoupledPlasma-AtomicEmission
mining or oil well drilling operations that may contain hazard-
Spectroscopy
ous or radioactive constituents, can include natural occurring
C1168 PracticeforPreparationandDissolutionofPlutonium
radioactive material (NORM).
Materials for Analysis
C1317 Practice for Dissolution of Silicate orAcid-Resistant 3.1.8 glass ceramic—solid material, partly crystalline and
Matrix Samples (Withdrawn 2001) partly glass. C162
C1463 Practices for Dissolving Glass Containing Radioac-
3.1.9 hazardous waste—(a) in a broad sense, any substance
tive and Mixed Waste for Chemical and Radiochemical
or mixture of substances having properties capable of produc-
Analysis
ing adverse effects on the health or safety of a human (see also
D1129 Terminology Relating to Water
RCRA hazardous waste); (b) any waste that is “listed” in
D4327 Test Method for Anions in Water by Suppressed Ion
40CFR Parts 261.31-261.33 or exhibits one or more of the
Chromatography
characteristics identified in 40CFR Parts 261.20–261.24, is a
2.2 Other Documents:
mixture of hazardous and nonhazardous waste, or is deter-
US EPA Standard SW846, Test Methods for Evaluating
mined to be hazardous waste by the generator.
Solid Waste
3.1.10 heavymetalcontaminatedwaste—acommonhazard-
Resource Conservation and Recovery Act (RCRA), 40CFR
ous waste; can damage organisms at low concentrations and
240-271, November 21, 1976
tends to accumulate in the food chain. Examples are lead,
DOE Methods for Evaluating Environmental and Waste
chromium, cadmium, and mercury.
Management Samples, March, 1993, DOE.EM-0089T,
3.1.11 high-level liquid waste (HLLW)—the radioactive
Rev. 1
aqueous waste resulting from the operation of the first cycle
Radioanalytical Technology for 10 CFR Part 61 and Other
extraction system, or equivalent concentrated wastes from
Selected Radionuclides, Literature Review, C. W.
subsequent extraction cycles, or equivalent wastes from a
Thomas, V. W. Thomas, and D. E. Robertson, PNNL-
processnotusingsolventextraction,inafacilityforprocessing
9444, March, 1996
irradiated reactor fuels.
3. Terminology
3.1.12 high-level radioactive waste (HLRW or HLW)—(a)
the highly radioactive material resulting from the reprocessing
3.1 Definitions:
of spent nuclear fuel, including liquid waste produced directly
3.1.1 analysis (physical or chemical)—the determination of
inreprocessingandanysolidmaterialderivedfromsuchliquid
physical or chemical properties or composition of a material.
waste that contains fission products (U.S. Code Title 42,
C859
Section 10101); (b) liquid wastes resulting from the operation
3.1.2 byproduct material—the tailings or wastes produced
of the first cycle solvent extraction system, or equivalent, and
by the extraction or concentration of uranium or thorium from
the concentrated wastes from subsequent extraction cycles, or
any ore processsed primarily for its source material content,
equivalent, in a facility for reprocessing irradiated reactor fuel.
including discrete surface wastes, resulting from uranium
3.1.13 homogeneous glass—(1) an inorganic product of
solution extraction processes. Underground ore bodies de-
fusion that has cooled to a rigid condition without crystallizing
pleted by such solution extraction operations do not constitute
(see Terminology C162); (2) a noncrystalline solid or an
“byproduct material.” 10 CFR Part 40
amorphous solid.
NOTE 1—A supplementary definition can be found in 10 CFR Part 20;
3.1.14 incidental waste—wastes that are not classified as
any radioactive material (except special nuclear material) yielded in, or
made radioactive by, exposure to the process of producing or utilizing HLW. NRC has defined three criteria that must be met for a
special nuclear material.
waste to be called incidental waste: (1) wastes that have been
3.1.3 calcine—to fire or heat a granular or particulate solid processed (or will be further processed) to remove key radio-
atlessthan,fusiontemperaturebutsufficienttoremovemostof
nuclides to the maximum extent that is technically and eco-
its chemically combined volatile matter (for example, H O, nomically practical; (2) wastes that will be incorporated in a
CO ) and otherwise to develop the desired properties for use. solid physical form at a concentration that does not exceed the
5 7
The last approved version of this historical standard is referenced on Code of Federal Regulations Title 40, Volume 19, Part 268.
www.astm.org. Varshneya, A. K., “Fundamentals of Inorganic Glasses,” Academic Press,
Perkins,W.W.,(Ed.),CeramicGlossary,TheAmericanCeramicSociety,1984. Boston, MA, 1994.
C1571 − 03 (2012)
applicable concentrations for Class C low-level waste; and (3) their normal operations. These wastes are generated in many
wastes that are to be managed pursuant of the Atomic Energy physical and chemical forms and levels of contamination 10
Act,sothatsafetyrequirementscomparabletotheperformance CFR Part 61
objectives set out in 10 CFR Part 61, Subpart C are satisfied.
3.1.21 mixed waste—waste that contains both hazardous
waste and source special nuclear or byproduct material subject
3.1.15 infrared incinerator—any enclosed device that uses
to the Atomic Energy Act (AEA) of 1954; The “radioactive
electric powered resistance heaters as a source of radiant heat
component”refersonlytotheactualradionuclidesdispersedor
followed by an afterburner using controlled flame combustion
suspended in the waste substance.
and which is not listed as an industrial furnace EPA 40 CFR
260.10 3.1.22 mixed waste glass—a glass comprised of glass form-
ing additives and hazardous waste that contains radioactive
3.1.16 incineration—(1) controlled flame combustion and
constituents.
neither meets the criteria for classification as a boiler, sludge
3.1.23 natural accelerator produced radioactive materials
dryer, or carbon regeneration unit, nor is listed as an industrial
(NARM)—radioactive materials not covered under the Atomic
furnace; or (2) meets the definition of infrared incinerator or
EnergyActof1954thatarenaturallyoccurringorproducedby
plasma arc incinerator EPA 40 CFR 260.10
an accelerator. Accelerators are used in sub-atomic particle
3.1.17 Joule heating—heating of glass by passing an elec-
physics research. These materials have been traditionally
tric current through it, the powerful stirring effect of the
regulated by States. NARM waste with more than 2 nCi/g of
convection currents created by electric heating causes unifor- 226
Ra or equivalent is commonly referred to as discrete
mity of temperature throughout the body of glass and makes it
NARM waste; below this threshold, the waste is referred to as
physically homogeneous.
diffuse NARM waste. NARM waste is not covered under the
3.1.18 loss-on-heating (LOH)—thepercentlossinweightof Atomic Energy Act, it is not a form of LLW, and it is not
regulated by Nuclear Regulatory Commission.
a material at a constant temperature ≥105°C , and for a time
long enough, to achieve constant weight, expressed as a
3.1.24 naturallyoccurringradioactivematerials(NORM)—
percent of the initial weight of the dry material; The fractional
NORM refers to materials not covered under the Atomic
or percentage weight loss of a material on heating in air from
Energy Act whose radioactivity has been enhanced (radionu-
an initial defined state (usually, dried) to a specified
clide concentrations are either increased or redistributed where
temperature, such as 1000°C, and holding there for a specified
they are more likely to cause exposure to man) usually by
period, such as 1 hour. Fixed procedures are designed, usually,
mineral extraction or processing activities. Examples are ex-
such that LOH represents the loss of combined H O, CO ,
2 2
ploration and production wastes from the oil and natural gas
certain other volatile inorganics, and combustible organic
industry and phosphate slag piles from the phosphate mining
matter.
industry.Thistermisnotusedtodescribeordiscussthenatural
radioactivity of rocks and soils, or background radiation, but
3.1.19 low-activity waste—the low-activity portion of
instead refers to materials whose radioactivity is technologi-
HLLW that is separated from the HLLW so that it can be
cally enhanced by controllable practices. Note this definition is
classified as LLW and be disposed of as “incidental waste.”
sometimes called technically enhanced NORM or TENORM.
3.1.20 low-level radioactive waste (LLRW or LLW)—(a)
3.1.25 plasma arc incinerator—any enclosed device using a
LLRW is waste that satisfies the definition of LLRW in the
high intensity electrical discharge or arc as a source of heat
Radioactive Waste Policy Amendments Act of 1985; radioac-
followed by an afterburner
...

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