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ASTM C1838-16

(Practice)

Standard Practice for Cleaning for 1S and 2S Bottles

Standard Practice for Cleaning for 1S and 2S Bottles

SIGNIFICANCE AND USE
4.1 The uranium hexfluoride (UF6), as described in Specifications C787 and C996, has to meet different requirements: one set of requirements being safety, health physics, and criticality and the other set being chemical, physical, and isotopic. To ensure the UF6 is in compliance with all requirements, sampling and analysis shall be performed. Therefore, packaging may have a significant impact on the quality of UF6.  
4.2 After sampling, the bottle will contain residues. There is contamination because of the equipment, other contamination caused by nonvolatile elements, and isotopic contamination as a result of UF6 hydrolysis.  
4.3 Cleaning shall be efficient. Special emphasis should be given to decontaminate the bottles without leaving any trace of cleaning products, make the bottles inert in UF6 medium (passivation bottle), and minimize waste. The cleaning process should be easy, safe, and environmentally friendly.  
4.4 This practice describes different protocols for cleaning bottles by gas and liquid.
SCOPE
1.1 This practice provides a description of the different ways to clean uranium hexafluoride (UF6) bottles.  
1.2 This practice describes two kinds of sample bottles: 1S and 2S bottles.  
1.3 Units—The values stated in SI units are to be regarded as the 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 and health practices and determine the applicability of regulatory limitations prior to use.

General Information

Status
Historical
Publication Date
31-Mar-2016
ICS
27.120.30 - Fissile materials and nuclear fuel technology
Technical Committee
C26 - Nuclear Fuel Cycle
Drafting Committee
C26.02 - Fuel and Fertile Material Specifications
Current Stage
Ref Project

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ASTM C1838-16 - Standard Practice for Cleaning for 1S and 2S Bottles
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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NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.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:C1838 −16
Standard Practice for
1
Cleaning for 1S and 2S Bottles
This standard is issued under the fixed designation C1838; 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 one set of requirements being safety, health physics, and
criticality and the other set being chemical, physical, and
1.1 This practice provides a description of the different
isotopic. To ensure the UF is in compliance with all
6
ways to clean uranium hexafluoride (UF ) bottles.
6
requirements, sampling and analysis shall be performed.
1.2 This practice describes two kinds of sample bottles: 1S
Therefore, packaging may have a significant impact on the
and 2S bottles.
quality of UF .
6
1.3 Units—The values stated in SI units are to be regarded
4.2 After sampling, the bottle will contain residues.There is
as the standard. No other units of measurement are included in
contamination because of the equipment, other contamination
this standard.
caused by nonvolatile elements, and isotopic contamination as
1.4 This standard does not purport to address all of the a result of UF hydrolysis.
6
safety concerns, if any, associated with its use. It is the
4.3 Cleaning shall be efficient. Special emphasis should be
responsibility of the user of this standard to establish appro-
given to decontaminate the bottles without leaving any trace of
priate safety and health practices and determine the applica-
cleaning products, make the bottles inert in UF medium
6
bility of regulatory limitations prior to use.
(passivation bottle), and minimize waste. The cleaning process
should be easy, safe, and environmentally friendly.
2. Referenced Documents
2 4.4 This practice describes different protocols for cleaning
2.1 ASTM Standards:
bottles by gas and liquid.
C787 Specification for Uranium Hexafluoride for Enrich-
ment
5. Description of Sample Bottles
C859 Terminology Relating to Nuclear Materials
5.1 Abottleiscomposedofacylinder,adaptors,andavalve
C996 Specification for Uranium Hexafluoride Enriched to
235
Less Than 5 % U (see Fig. 1).
3
2.2 ANSI Standard:
5.2 Adaptorsarebrazedorweldedonthevalveandscrewed
N14.1 Nuclear Materials—Uranium Hexafluoride—
on the cylinder.
Packaging for Transport
5.3 Bottles and valves are made from nickel or nickel-
copper alloy (for example, Monel).
3. Terminology
5.4 The design pressure and temperature are indicated in
3.1 Definitions—Definitions of terms are as given in Termi-
ANSI N14.1.
nology C859.
4. Significance and Use 6. Reagents
4.1 The uranium hexfluoride (UF ), as described in Speci- 6.1 Purity of Reagents—Reagent-grade chemicals shall be
6
fications C787 and C996, has to meet different requirements: used in all tests. Unless otherwise indicated, it is intended that
all reagents conform to the specifications of the Committee on
Analytical Reagents of the American Chemical Society where
1
This practice is under the jurisdiction of ASTM Committee C26 on Nuclear 4
such specifications are available. Other grades may be used,
Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel and
provided it is first ascertained that the reagent is of sufficiently
Fertile Material Specifications.
Current edition approved April 1, 2016. Published May 2016. DOI: 10.1520/
C1838–16.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
4
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM Reagent Chemicals, American Chemical Society Specifications, American
Standards volume information, refer to the standard’s Document Summary page on Chemical Society, Washington, DC. For suggestions on the testing of reagents not
the ASTM website. listed by the American Chemical Society, see Analar Standards for Laboratory
3
Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St., Chemicals,BDHLtd.,Poole,Dorset,U.K.andthe United States Pharmacopeia and
4th Floor, New York, NY 10036, http://www.ansi.org. National Formulary, U.S. Pharmacopeial Convention, Inc. (USPC), Rockville, MD.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C1838−16
TABLE 2 Chrome Trioxide, Sulfuric Acid, and Hydrofluoric Acid
Composition
% (in weight)
Chrome Trioxide CrO 5to10
3
Sulfuric Acid H SO 5to15
2 4
Hydrofluoric Acid HF 1 to 7
6.6.1 Composition—The concentration specified is about
100gK CO /L.
2 3
6.6.2 Hazards—Irritation and corrosion of the skin, the
eyes, and the respiratory and digestive tracts.
6.7 Hydrogen Peroxide (H O ):
2 2
6.7.1 Composition—The concentr
...

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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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Procedure Number  
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Section  
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10  
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18  
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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).  
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1.2.2 Grade F—240Pu / (Pu + Am) isotope mass fraction is at least 7 % and less than 19 %.  
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4.1 Materials handling equipment operability and long-term integrity are concerns that originate during the design and fabrication sequences. Such concerns are most efficiently addressed during one or the other of these stages. Equipment operability and integrity can be compromised during handling and installation sequences. For this reason, the subject equipment should be handled and installed under closely controlled and supervised conditions.  
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4.5.2 Materials handling equipment should be capable of withstanding rigorous chemical cleaning and decontamination procedures.  
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SCOPE
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1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.  
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SCOPE
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.
SCOPE
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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