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ASTM C1295-13

(Test Method)

Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate Solution

Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate Solution

SIGNIFICANCE AND USE
4.1 Specific gamma-ray emitting radionuclides in UF6 are identified and quantified using a high-resolution gamma-ray energy analysis system, which includes a high-resolution germanium detector. This test method shall be used to meet the health and safety specifications of C787, C788, and C996 regarding applicable fission products in reprocessed uranium solutions. This test method may also be used to provide information to parties such as conversion facilities on the level of uranium decay products in such materials.
SCOPE
1.1 This test method covers the measurement of gamma energy emitted from fission and decay products in uranium hexafluoride (UF6) and uranyl nitrate solution. It is intended to provide a method for demonstrating compliance with UF6 specifications C787 and C996 and uranyl nitrate specification C788.  
1.2 The lower limit of detection is 5000 MeV Bq/kg (MeV/kg per second) of uranium and is the square root of the sum of the squares of the individual reporting limits of the nuclides to be measured. The limit of detection was determined on a pure, aged natural uranium (ANU) solution. The value is dependent upon detector efficiency and background.  
1.3 The nuclides to be measured are 106Ru/ 106Rh, 103Ru, 137Cs,  144Ce,  144Pr,  141Ce,  95Zr,  95Nb, and  125Sb. Other gamma energy-emitting fission nuclides present in the spectrum at detectable levels should be identified and quantified as required by the data quality objectives.  
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 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
14-Feb-2013
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 C1295-14 - Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate Solution
Effective Date
15-Jun-2014

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ASTM C1295-13 - Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate SolutionASTM C1295-13 - Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate Solution
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REDLINE ASTM C1295-13 - Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate SolutionREDLINE ASTM C1295-13 - Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate Solution
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Standards Content (Sample)

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:C1295 −13
StandardTest Method for
Gamma Energy Emission from Fission and Decay Products
1
in Uranium Hexafluoride and Uranyl Nitrate Solution
This standard is issued under the fixed designation C1295; 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 (´) indicates an editorial change since the last revision or reapproval.
1. Scope Uranium Hexafluoride
C787Specification for Uranium Hexafluoride for Enrich-
1.1 This test method covers the measurement of gamma
ment
energy emitted from fission and decay products in uranium
C788Specification for Nuclear-Grade Uranyl Nitrate Solu-
hexafluoride (UF ) and uranyl nitrate solution. It is intended to
6
tion or Crystals
provide a method for demonstrating compliance with UF
6
C996Specification for Uranium Hexafluoride Enriched to
specifications C787 and C996 and uranyl nitrate specification
235
Less Than 5 % U
C788.
D3649PracticeforHigh-ResolutionGamma-RaySpectrom-
1.2 The lower limit of detection is 5000 MeV Bq/kg
etry of Water
(MeV/kg per second) of uranium and is the square root of the
sum of the squares of the individual reporting limits of the
3. Summary of Test Method
nuclidestobemeasured.Thelimitofdetectionwasdetermined
3.1 A solution of the uranium sample is counted on a
on a pure, aged natural uranium (ANU) solution. The value is
high-resolutiongamma-rayspectrometrysystem.Theresulting
dependent upon detector efficiency and background.
spectrum is analyzed to determine the identity and activity of
106 106 103
1.3 The nuclides to be measured are Ru/ Rh, Ru,
the gamma-ray-emitting radioactive fission and decay prod-
137 144 144 141 95 95 125
Cs, Ce, Pr, Ce, Zr, Nb, and Sb. Other gamma
ucts. The number of counts recorded from one or more of the
energy-emitting fission nuclides present in the spectrum at
peaks identified with each fission nuclide is converted to
detectablelevelsshouldbeidentifiedandquantifiedasrequired
disintegrationsofthatnuclidepersecond(Bq).Thegamma-ray
by the data quality objectives.
energy for a fission nuclide is calculated by multiplying the
number of disintegrations per second of the nuclide by the
1.4 The values stated in SI units are to be regarded as
mean gamma-ray energy emission rate of the nuclide. The
standard. No other units of measurement are included in this
standard. calculated gamma-ray energy emission rates for all observed
fission nuclides are summed, then divided by the mass of the
1.5 This standard does not purport to address all of the
uranium in the sample to calculate the overall rate of gamma
safety concerns, if any, associated with its use. It is the
energy production in units of million electron volts per second
responsibility of the user of this standard to establish appro-
per kilogram of uranium. Decay product nuclides will be
priate safety and health practices and determine the applica-
separately quantified and reported based on specific needs.
bility of regulatory limitations prior to use.
4. Significance and Use
2. Referenced Documents
2
4.1 Specific gamma-ray emitting radionuclides in UF are
6
2.1 ASTM Standards:
identified and quantified using a high-resolution gamma-ray
C761Test Methods for Chemical, Mass Spectrometric,
energy analysis system, which includes a high-resolution
Spectrochemical, Nuclear, and RadiochemicalAnalysis of
germaniumdetector.Thistestmethodshallbeusedtomeetthe
health and safety specifications of C787, C788, and C996
regarding applicable fission products in reprocessed uranium
1
ThistestmethodisunderthejurisdictionofASTMCommitteeC26onNuclear
Fuel Cycle and is the direct responsibility of Subcommittee C26.05 on Methods of solutions. This test method may also be used to provide
Test.
information to parties such as conversion facilities on the level
Current edition approved Feb. 15, 2013. Published March 2013. Originally
of uranium decay products in such materials.
approved in 1995. Last previous edition approved in 2005 as C1295–05. DOI:
10.1520/C1295-13.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or 5. Apparatus
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
5.1 High-Resolution Gamma-Ray Spectrometry System, as
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. specified in Practice D3649.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C1295−13
5.2 SampleContainerwithFittedCap—Aleak-proofplastic count duration (live time) to determine the rate in counts per
container capable of holding the required sample volume. The second for each radionuclide.
...

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: C1295 − 05 C1295 − 13
Standard Test Method for
Gamma Energy Emission from Fission and Decay Products
1
in Uranium Hexafluoride and Uranyl Nitrate Solution
This standard is issued under the fixed designation C1295; 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 test method covers the measurement of gamma energy emitted from fission and decay products in uranium hexafluoride
(UF ) and uranyl nitrate solution. It is intended to provide a method for demonstrating compliance with UF specifications C787
6 6
and C996 and uranyl nitrate specification C788.
1.2 The lower limit of detection is 5000 MeV Bq/kg (MeV/kg per second) of uranium and is the square root of the sum of the
squares of the individual reporting limits of the nuclides to be measured. The limit of detection was determined on a pure, aged
natural uranium (ANU) solution. The value is dependent upon detector efficiency and background.
106 106 103
1.3 The nuclides to be measured are Ru/ Rh, Ru,
137 144 144 141 95 95 125
Cs, Ce, Pr, Ce, Zr, Nb, and Sb. Other gamma energy-emitting fission nuclides present in the spectrum at
detectable levels should be identified and quantified as required by the data quality objectives.
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 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.
2. Referenced Documents
2
2.1 ASTM Standards:
C761 Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Uranium
Hexafluoride
C787 Specification for Uranium Hexafluoride for Enrichment
C788 Specification for Nuclear-Grade Uranyl Nitrate Solution or Crystals
235
C996 Specification for Uranium Hexafluoride Enriched to Less Than 5 % U
D3649 Practice for High-Resolution Gamma-Ray Spectrometry of Water
3. Summary of Test Method
3.1 A solution of the uranium sample is counted on a high-resolution gamma-ray spectroscopyspectrometry system. The
resulting spectrum is analyzed to determine the identity and activity of the gamma-ray-emitting radioactive fission and decay
products. The number of counts recorded from one or more of the peaks identified with each fission nuclide is converted to
disintegrations of that nuclide per second (Bq). The gamma-ray energy for a fission nuclide is calculated by multiplying the number
of disintegrations per second of the nuclide by the mean gamma-ray energy emission rate of the nuclide. The calculated gamma-ray
energy emission rates for all observed fission nuclides are summed, then divided by the mass of the uranium in the sample to
calculate the overall rate of gamma energy production in units of million electron volts per second per kilogram of uranium. Decay
product nuclides will be separately quantified and reported based on specific needs.
4. Significance and Use
4.1 TheSpecific gamma-ray emitting fission products radionuclides in UF are identified and quantified using a high-resolution
6
gamma-ray energy analysis system, which includes a high-resolution germanium detector. This test method shall be used to meet
1
This test method is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.05 on Methods of Test.
Current edition approved July 1, 2005Feb. 15, 2013. Published August 2005March 2013. Originally approved in 1995. Last previous edition approved in 19982005 as
C1295 – 98.C1295 – 05. DOI: 10.1520/C1295-05.10.1520/C1295-13.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at service@astm.org. 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 ----------------------
C1295 − 13
the health and safety specifications of C787, C788, and C996 regarding applicable fission products in reprocessed uranium
solutions. This test method may
...

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4.5 This service imposes stringent requirements on the quality and the integrity of the equipment, as follows:  
4.5.1 Boots and similar protective covers should not restrict movement of the equipment, should be properly sealed to the equipment and should withstand the radiation, cell atmosphere, dust, cell temperatures, chemical exposures, and cleaning and decontamination reagents, and also resist snags and tearing.  
4.5.2 Materials handling equipment should be capable of withstanding rigorous chemical cleaning and decontamination procedures.  
4.5.3 Materials handling equipment should be designed and fabricated to remain dimensionally stable throughout its life cycle.  
4.5.4 Attention to fabrication tolerances is necessary to allow the proper fit-up between components for the proper installation and mounting of materials handling equipment in hot cells, for example, when parts or components are being replaced. Fabrication tolerances should be controlled to provide sufficie...
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1.1 Intent:  
1.1.1 This guide covers materials handling equipment used in hot cells (shielded cells) for the processing and handling of nuclear and radioactive materials. The intent of this guide is to aid in the selection and design of materials handling equipment for hot cells in order to minimize equipment failures and maximize the equipment utility.  
1.1.2 It is intended that this guide record the principles and caveats that experience has shown to be essential to the design, fabrication, installation, maintenance, repair, replacement, and decontamination and decommissioning of materials handling equipment capable of meeting the stringent demands of operating, dependably and safely, in a hot cell environment where operator visibility is limited due to the radiation exposure hazards.  
1.1.3 This guide may apply to materials handling equipment in other radioactive remotely operated facilities such as suited entry repair areas and canyons, but does not apply to materials handling equipment used in commercial power reactors.  
1.1.4 This guide covers mechanical master-slave manipulators and electro-mechanical manipulators, but does not cover electro-hydraulic manipulators.  
1.2 Applicability:  
1.2.1 This guide is intended to be applicable to equipment used under one or more of the following conditions:
1.2.1.1 The materials handled or processed constitute a significant radiation hazard to man or to the environment.
1.2.1.2 The equipment will generally be used over a long-term life cycle (for example, in excess of two years), but equipment intended for use over a shorter life cycle is not excluded.
1.2.1.3 The equipment can neither be accessed directly for purposes of operation or maintenance, nor can the equipment be viewed directly, for example, without shielded viewing windows, periscopes, or a video monitoring system.  
1.3 User Caveats:  
1.3.1 This standard is not a substitute for applied engin...

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ASTM
ASTM C1108-23(Test Method)
Standard Test Method for Plutonium by Controlled-Potential Coulometry

SIGNIFICANCE AND USE
5.1 Factors governing selection of a method for the determination of plutonium include available quantity of sample, sample purity, desired level of reliability, and equipment.  
5.1.1 This test method determines 5 mg to 20 mg of plutonium with prior dissolution using Practice C1168.  
5.1.2 This test method calculates plutonium mass fraction in solutions and solids using an electrical calibration based upon Ohm’s Law and the Faraday Constant.  
5.1.3 Chemical standards are used for quality control. When prior chemical separation of plutonium is necessary to remove interferences, the quality control standards should be included with each chemical separation batch (9).  
5.2 Fitness for Purpose of Safeguards and Nuclear Safety Application—Methods intended for use in safeguards and nuclear safety applications shall meet the requirements specified by Guide C1068 for use in such applications.
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1.1 This test method describes the determination of dissolved plutonium from unirradiated nuclear-grade (that is, high-purity) materials by controlled-potential coulometry. Controlled-potential coulometry may be performed in a choice of supporting electrolytes, such as 0.9 mol/L (0.9 M) HNO3, 1 mol/L (1 M) HClO4, 1 mol/L (1 M) HCl, 5 mol/L (5 M) HCl, and 0.5 mol/L (0.5 M) H2SO4. Limitations on the use of selected supporting electrolytes are discussed in Section 6. Optimum quantities of plutonium for this procedure are 5 mg to 20 mg.  
1.2 Plutonium-bearing materials are radioactive and toxic. Adequate laboratory facilities, such as gloved boxes, fume hoods, controlled ventilation, etc., along with safe techniques must be used in handling specimens containing these materials.  
1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.  
1.4 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.  
1.5 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.

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ASTM
ASTM C1204-14(2023)(Test Method)
Standard Test Method for Uranium in Presence of Plutonium by Iron(II) Reduction in Phosphoric Acid Followed by Chromium(VI) Titration

SIGNIFICANCE AND USE
4.1 Factors governing selection of a method for the determination of uranium include available quantity of sample, sample purity, desired level of reliability, and equipment availability.  
4.2 This test method is suitable for samples between 20 mg to 300 mg of uranium, is applicable to fast breeder reactor (FBR)-mixed oxides having a uranium to plutonium ratio of 2.5 and greater, is tolerant towards most metallic impurity elements usually specified for FBR-mixed oxide fuel, and uses no special equipment.  
4.3 The ruggedness of the titration method has been studied for both the volumetric (6) and the weight (7) titration of uranium with dichromate.
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1.1 This test method covers unirradiated uranium-plutonium mixed oxide having a uranium to plutonium ratio of 2.5 and greater. The presence of larger amounts of plutonium (Pu) that give lower uranium to plutonium ratios may give low analysis results for uranium (U) (1)2, if the amount of plutonium together with the uranium is sufficient to slow the reduction step and prevent complete reduction of the uranium in the allotted time. Use of this test method for lower uranium to plutonium ratios may be possible, especially when 20 mg to 50 mg quantities of uranium are being titrated rather than the 100 mg to 300 mg in the study cited in Ref (1). Confirmation of that information should be obtained before this test method is used for ratios of uranium to plutonium less than 2.5.  
1.2 The amount of uranium determined in the data presented in Section 12 was 20 mg to 50 mg. However, this test method, as stated, contains iron in excess of that needed to reduce the combined quantities of uranium and plutonium in a solution containing 300 mg of uranium with uranium to plutonium ratios greater than or equal to 2.5. Solutions containing up to 300 mg uranium with uranium to plutonium ratios greater than or equal to 2.5 have been analyzed (1) using the reagent volumes and conditions as described in Section 10.  
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.4 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. For specific hazard statements, see Section 8.  
1.5 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.

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ASTM
ASTM C1347-08(2023)(Practice)
Standard Practice for Preparation and Dissolution of Uranium Materials for Analysis

SIGNIFICANCE AND USE
4.1 The materials covered that must meet ASTM specifications are uranium metal and uranium oxide.  
4.2 Uranium materials are used as nuclear reactor fuel. For this use, these materials must meet certain criteria for uranium content, uranium-235 enrichment, and impurity content, as described in Specifications C753 and C776. The material is assayed for uranium to determine whether the content is as specified.  
4.3 Uranium alloys, refractory uranium materials, and uranium containing scrap and ash are unique uranium materials for which the user must determine the applicability of this practice. In general, these unique uranium materials are dissolved with various acid mixtures or by fusion with various fluxes.
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1.1 This practice covers dissolution treatments for uranium materials that are applicable to the test methods used for characterizing these materials for uranium elemental, isotopic, and impurities determinations. Dissolution treatments for the major uranium materials assayed for uranium or analyzed for other components are listed.  
1.2 The treatments, in order of presentation, are as follows:    
Procedure Title  
Section  
Dissolution of Uranium Metal and Oxide with Nitric Acid  
8.1  
Dissolution of Uranium Oxides with Nitric Acid and Residue
Treatment  
8.2  
Dissolution of Uranium-Aluminum Alloys in Hydrochloric Acid
with Residue Treatment  
8.3  
Dissolution of Uranium Scrap and Ash by Leaching with Nitric
Acid and Treatment of Residue by Carbonate Fusion  
8.4  
Dissolution of Refractory Uranium-Containing Material by
Carbonate Fusion  
8.5  
Dissolution of Uranium—Aluminum Alloys
Uranium Scrap and Ash, and Refractory
Uranium-Containing Materials by
Microwave Treatment  
8.6  
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.4 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. Specific hazards statements are given in Section 7.  
1.5 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.

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