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ASTM C1284-00

(Practice)

Standard Practice for Electrodeposition of the Actinides for Alpha Spectrometry

Standard Practice for Electrodeposition of the Actinides for Alpha Spectrometry

SCOPE
1.1 This practice covers the preparation of separated actinide fractions for alpha spectrometry measurement.  It is applicable to any of the actinides that can be dissolved in dilute ammonium sulfate solution. Examples of applicable actinide fractions would be the final elution from an ion exchange separation or the final strip from a solvent extraction separation.
1.2  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.

General Information

Status
Historical
Publication Date
09-Jan-2000
ICS
27.120.30 - Fissile materials and nuclear fuel technology
Technical Committee
C26 - Nuclear Fuel Cycle
Drafting Committee
C26.05 - Methods of Test
Current Stage
Ref Project

Relations

Replaced By
ASTM C1284-00(2005) - Standard Practice for Electrodeposition of the Actinides for Alpha Spectrometry
Effective Date
01-Jun-2005
Referred By
ASTM C1000-19 - Standard Test Method for Radiochemical Determination of Uranium Isotopes in Soil by Alpha Spectrometry
Effective Date
10-Jan-2000
Referred By
ASTM C1001-19 - Standard Test Method for Radiochemical Determination of Plutonium in Soil by Alpha Spectroscopy
Effective Date
10-Jan-2000
Referred By
ASTM C1475-17 - Standard Guide for Determination of Neptunium-237 in Soil
Effective Date
10-Jan-2000
Referred By
ASTM C1473-19 - Standard Test Method for Radiochemical Determination of Uranium Isotopes in Urine by Alpha Spectrometry
Effective Date
10-Jan-2000
Referred By
ASTM D7939-15 - Standard Test Method for Rapid Radiochemical Determination of Americium-241 in Water (Withdrawn 2024)
Effective Date
10-Jan-2000
Referred By
ASTM D3865-09(2015) - Standard Test Method for Plutonium in Water (Withdrawn 2024)
Effective Date
10-Jan-2000
Referred By
ASTM C1636-22 - Standard Guide for Determination of Uranium-232 in Uranium Hexafluoride
Effective Date
10-Jan-2000
Referred By
ASTM C1163-14(2023) - Standard Practice for Mounting Actinides for Alpha Spectrometry Using Neodymium Fluoride
Effective Date
10-Jan-2000

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ASTM C1284-00 - Standard Practice for Electrodeposition of the Actinides for Alpha SpectrometryASTM C1284-00 - Standard Practice for Electrodeposition of the Actinides for Alpha Spectrometry
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ASTM C1284-00 - Standard Practice for Electrodeposition of the Actinides for Alpha Spectrometry
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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:C1284–00
Standard Practice for
Electrodeposition of the Actinides for Alpha Spectrometry
This standard is issued under the fixed designation C1284; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (e) indicates an editorial change since the last revision or reapproval.
1. Scope resultant electrodeposited samples are suitable for alpha spec-
trometry measurements.
1.1 This practice covers the preparation of separated ac-
tinide fractions for alpha spectrometry measurement. It is
4. Significance and Use
applicabletoanyoftheactinidesthatcanbedissolvedindilute
4.1 The determination of actinide elements by alpha spec-
ammonium sulfate solution. Examples of applicable actinide
trometry measurement is an essential part of many environ-
fractions would be the final elution from an ion exchange
mental research and monitoring programs.Alpha spectrometry
separation or the final strip from a solvent extraction separa-
measurementsidentifyandquantifythealpha-emittingactinide
tion.
elements. A variety of separation methods will typically
1.2 This standard does not purport to address all of the
preceed the electrodeposition of a sample for alpha spectrom-
safety concerns, if any, associated with its use. It is the
etry measurements. In addition to the electrodeposition proce-
responsibility of the user of this standard to establish appro-
dure presented in this practice, the scientific literature contains
priate safety and health practices and determine the applica-
other procedures for actinide electrodeposition.
bility of regulatory limitations prior to use.
NOTE 1—An alternate method for mounting actinides for alpha spec-
2. Referenced Documents
trometry measurements by coprecipitation with neodymium fluoride is
described in Test Methods C1163.
2.1 ASTM Standards:
C 1000 Test Method for Radiochemical Determination of
5. Interferences
Uranium Isotopes in Soil by Alpha Spectrometry
5.1 Any element present in the separated fraction which is
C 1001 Test Method for Radiochemical Determination of
capable of cathodic electrodeposition will be present on the
Plutonium in Soil by Alpha Spectrometry
metal disc. In particular Po (5.30 MeV) deposited on the
C 1163 Test Methods for Mounting Actinides for Alpha
disc would interfere with the yield determination of U (5.32
Spectrometry Using Neodymium Fluoride
MeV) or Am (5.28 MeV) tracers used in the determination
C 1205 Test Method for the Radiochemical Determination
of isotopic uranium and Am, respectively.
of Americium-241 in Soil by Alpha Spectrometry
5.2 Incomplete separation of rare earth elements or incom-
D 1193 Specification for Reagent Water
plete wet ashing for the removal of organic material will
3. Summary of Practice
decrease the efficiency of the electrodeposition and may result
in a thick deposit unsuitable for alpha spectrometry measure-
3.1 Guidance is provided for the electrodeposition of sepa-
ment.
rated actinide fractions onto metal discs.This practice is based
−2
5.3 The quantity of actinide should be such that <5 µg cm
on cathodic deposition of the hydrated oxides of the actinides
are electrodeposited on the metal disc. Thicker deposits are
from an acidic medium containing an ammonium salt. The
typically unsuitable for measurement by alpha spectrometry
due to the resulting attenuation and decrease in energy resolu-
tion.
This practice is under the jurisdiction of ASTM Committee C-26 on Nuclear
Fuel Cycle and is the direct responsibility of Subcommittee C26.05 on Methods of
6. Apparatus
Test.
6.1 Electrodeposition Power Supply—Constant current, ad-
Current edition approved Jan. 10, 2000. Published February 2000. Originally
published as C1284-94. Last previous edition C1284-94.
justable from 0 to 2 A with indicating meter.
Based on Talvitie, N. A., “Electrodeposition of Actinides for Alpha Spectro-
6.2 Electrodeposition Cell—Disposable cells are recom-
metric Determination,” Analytical Chemistry, Vol 44, 1972, pp. 280–283.
mended.The cells should have a minimum volume capacity of
Annual Book of ASTM Standards, Vol 12.01.
Annual Book of ASTM Standards, Vol 11.01. 25 mL.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
C1284
6.3 Metal Discs— Stainless steel disc, or other metal disc 7.9 Sodium Hydrogen Sulfate (0.36 M in1MH SO )—
2 4
such as platinum, polished to a mirror finish on one side. The Dissolve10gofNaHSO ·H Oin88mLofwaterandadd112
4 2
diameter of the disc is determined by diameter of the elec- mL of 1.8 M H SO .
2 4
trodepositioncell.Thecurrentdensityshouldbeapproximately 7.10 Sulfuric Acid (1.8 M)—Mix 100 mL of concentrated
−2
0.5Acm of the disc area. sulfuric acid
...

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5.1 This test method can be used on plutonium matrices in nitrate solutions.  
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5.1 Plutonium and uranium mixtures are used as nuclear reactor fuels. For use as a nuclear reactor fuel, the material must meet certain criteria for combined uranium and plutonium content, effective fissile content, and impurity content as described in Specifications C757 and C833. After dissolution using one of the procedures described in this practice, the material is assayed for plutonium and uranium to determine if the content is correct as specified by the purchaser.  
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1.1 This practice is a compilation of dissolution techniques for plutonium materials that are applicable to the test methods used for characterizing these materials. Dissolution treatments for the major plutonium materials assayed for plutonium or analyzed for other components are listed. Aliquots of the dissolved materials are dispensed on a mass basis when one of the analyses must be of high precision, such as plutonium assay; otherwise they are dispensed on a volume basis.  
1.2 Procedures in this practice are intended for the dissolution of plutonium metal, plutonium oxide, and uranium-plutonium mixed oxides. Aliquots of dissolved materials are analyzed using test methods, such as those developed by Subcommittee C26.05 on Methods of Test, to demonstrate compliance with applicable requirements. These may include product specifications such as Specifications C757 and C833.  
1.3 One or more of the procedures in this practice may be applicable to unique plutonium materials, such as alloys, compounds, and scrap materials. The user must determine the applicability of this practice to such materials.  
1.4 The treatments, in order of presentation, are as follows:    
Procedure Number  
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Section  
1  
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Dissolution of Plutonium Metal with Hydrochloric Acid and Heating  
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10  
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18  
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Standard Test Method for Quantitative Determination of 241Am in Plutonium by Gamma-Ray Spectrometry

SIGNIFICANCE AND USE
5.1 This test method allows the determination of 241Am in a plutonium solution without separation of the americium from the plutonium. It is generally applicable to any solution containing 241Am.  
5.2 The 241Am in solid plutonium materials may be determined when these materials are dissolved (see Practice C1168).  
5.3 When the plutonium solution contains unacceptable levels of fission products or other materials, this method may be used following a tri-n-octylphosphine oxide (TOPO) extraction, ion exchange or other similar separation techniques (see Test Methods C758 and C759).  
5.4 This test method is less subject to interferences from plutonium than alpha counting since the energy of the gamma ray used for the analysis is better resolved from other gamma rays than the alpha particle energies used for alpha counting.  
5.5 The minimal sample preparation reduces the amount of sample handling and exposure to the analyst.  
5.6 This test method is applicable only to homogeneous solutions. This test method is not suitable for solutions containing solids.  
5.7 Solutions containing 241Am at concentrations as little as 1 × 10−5 g/L may be analyzed using this method. The lower limit depends on the detector used and the counting geometry. Solutions containing high concentrations may be analyzed following an appropriate dilution.
SCOPE
1.1 This test method covers the quantitative determination of 241Am by gamma-ray spectrometry in plutonium nitrate solution samples that do not contain significant amounts of radioactive fission products or other high specific activity gamma-ray emitters.  
1.2 This test method can be used to determine the 241Am in samples of plutonium metal, oxide and other solid forms, when the solid is appropriately sampled and dissolved.  
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5.1 Uranium hexafluoride is a basic material used to produce nuclear reactor fuel. To be suitable for this purpose, the material must meet criteria for isotopic composition. This test method is designed to determine whether the material meets the requirements described in Specifications C787 and C996.
SCOPE
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ASTM C833-23(Specification)
Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors

ABSTRACT
This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. The diversity of manufacturing methods shall be recognized by which uranium-plutonium dioxide pellets are produced and the many special requirements for chemical and physical characterization that may be imposed by the operating conditions to which the pellets will be subjected in specific reactor systems. The following are different chemical requirements that shall be determined: uranium content, plutonium content, impurity content, stoichiometry, moisture content, gas content, and americium-241 content. Nuclear requirements such as isotopic content, plutonium equivalent at a given date, equivalent boron content, and reactivity shall also be determined. Physical properties of the pellets like dimensions, density, grain size, pore morphology, plutonium-oxide homogeneity, plutonium-oxide particle size, plutonium-oxide particle distribution, integrity, and surface cracks shall be determined as well. The surfaces of finished pellets shall be visually free of loose chips, oil, macroscopic inclusions, and foreign materials. An estimate of the fuel pellet irradiation stability shall be obtained unless adequate allowance for such effects are factored into the fuel rod design. The estimate of the stability shall consist of either conformance to the thermal stability test as specified in the or by adequate correlation of manufacturing process or microstructure to in-reactor behavior, or both.
SCOPE
1.1 This specification covers finished sintered and ground (U, Pu)O2 pellets for use in light water reactors. It applies to (U, Pu)O2 pellets containing a plutonium mass fraction up to 15 % (that is, mass of Pu divided by the sum of masses U, Pu, and Am yielding 0.15 or less).  
1.2 Pellets produced under this specification are available in four grades.  
1.2.1 Grade R—240Pu / (Pu + Am) isotope mass fraction is at least 19 %.  
1.2.2 Grade F—240Pu / (Pu + Am) isotope mass fraction is at least 7 % and less than 19 %.  
1.2.3 Grade N1—240Pu / (Pu + Am) isotope mass fraction is less than 7 %.  
1.2.4 Grade N2—240Pu /239Pu isotope mass fraction does not exceed 0.10 (10 %).  
1.3 There is no discussion of or provision for preventing criticality incidents, nor are health and safety requirements, the avoidance of hazards, or shipping precautions and controls discussed. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, federal, state, and local regulations pertaining to possessing, processing, shipping, or using source or special nuclear material. Examples of U.S. government documents are Code of Federal Regulations Title 10, Part 50—Domestic Licensing of Production and Utilization Facilities; Code of Federal Regulations Title 10, Part 71—Packaging and Transportation of Radioactive Material; and Code of Federal Regulations Title 49, Part 173—General Requirements for Shipments and Packaging.  
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.5 The following safety hazards caveat pertains only to the technical requirements portion, Section 4, of this specification: 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.  
1.6 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 Technic...

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ASTM
ASTM C1062-23(Guide)
Standard Guide for Design, Fabrication, and Installation of Nuclear Fuel Dissolution Facilities

SIGNIFICANCE AND USE
4.1 The purpose of this guide is to provide information that will help to ensure that nuclear fuel dissolution facilities are conceived, designed, fabricated, constructed, and installed in an economic and efficient manner. This guide will help facilities meet the intended performance functions, eliminate or minimize the possibility of nuclear criticality and provide for the protection of both the operator personnel and the public at large under normal and abnormal (emergency) operating conditions as well as under credible failure or accident conditions.
SCOPE
1.1 It is the intent of this guide to set forth criteria and procedures for the design, fabrication and installation of nuclear fuel dissolution facilities. This guide applies to and encompasses all processing steps or operations beyond the fuel shearing operation (not covered), up to and including the dissolving accountability vessel.  
1.2 Applicability and Exclusions:  
1.2.1 Operations—This guide does not cover the operation of nuclear fuel dissolution facilities. Some operating considerations are noted to the extent that these impact upon or influence design.
1.2.1.1 Dissolution Procedures—Fuel compositions, fuel element geometry, and fuel manufacturing methods are subject to continuous change in response to the demands of new reactor designs and requirements. These changes preclude the inclusion of design considerations for dissolvers suitable for the processing of all possible fuel types. This guide will only address equipment associated with dissolution cycles for those fuels that have been used most extensively in reactors as of the time of issue (or revision) of this guide. (See Appendix X1.)  
1.2.2 Processes—This guide covers the design, fabrication and installation of nuclear fuel dissolution facilities for fuels of the type currently used in Pressurized Water Reactors (PWR). Boiling Water Reactors (BWR), Pressurized Heavy Water Reactors (PHWR) and Heavy Water Reactors (HWR) and the fuel dissolution processing technologies discussed herein. However, much of the information and criteria presented may be applicable to the equipment for other dissolution processes such as for enriched uranium-aluminum fuels from typical research reactors, as well as for dissolution processes for some thorium and plutonium-containing fuels and others. The guide does not address equipment design for the dissolution of high burn-up or mixed oxide fuels.
1.2.2.1 This guide does not address special dissolution processes that may require substantially different equipment or pose different hazards than those associated with the fuel types noted above. Examples of precluded cases are electrolytic dissolution and sodium-bonded fuels processing. The guide does not address the design and fabrication of continuous dissolvers.  
1.2.3 Ancillary or auxiliary facilities (for example, steam, cooling water, electrical services) are not covered. Cold chemical feed considerations are addressed briefly.  
1.2.4 Dissolution Pretreatment—Fuel pretreatment steps incidental to the preparation of spent fuel assemblies for dissolution reprocessing are not covered by this guide. This exclusion applies to thermal treatment steps such as “Voloxidation” to drive off gases prior to dissolution, to mechanical decladding operations or process steps associated with fuel elements disassembly and removal of end fittings, to chopping and shearing operations, and to any other pretreatment operations judged essential to an efficient nuclear fuels dissolution step.  
1.2.5 Fundamentals—This guide does not address specific chemical, physical or mechanical technology, fluid mechanics, stress analysis or other engineering fundamentals that are also applied in the creation of a safe design for nuclear fuel dissolution facilities.  
1.3 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI unit...

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