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ASTM C1838-16(2021)

(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, 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.

General Information

Status
Published
Publication Date
30-Sep-2021
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

Relations

Refers
ASTM C996-20 - Standard Specification for Uranium Hexafluoride Enriched to Less Than 5&#x2009;%&#x2009;<sup > 235</sup>U
Effective Date
01-Mar-2020
Refers
ASTM C787-20 - Standard Specification for Uranium Hexafluoride for Enrichment
Effective Date
01-Mar-2020

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ASTM C1838-16(2021) - Standard Practice for Cleaning for 1S and 2S BottlesASTM C1838-16(2021) - Standard Practice for Cleaning for 1S and 2S Bottles
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ASTM C1838-16(2021) - Standard Practice for Cleaning for 1S and 2S Bottles
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Standards Content (Sample)

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.
Designation: C1838 −16 (Reapproved 2021)
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 3. Terminology
1.1 This practice provides a description of the different 3.1 Definitions—Definitions of terms are as given in Termi-
ways to clean uranium hexafluoride (UF ) bottles.
nology C859.
6
1.2 This practice describes two kinds of sample bottles: 1S
4. Significance and Use
and 2S bottles.
4.1 The uranium hexfluoride (UF ), as described in Speci-
6
1.3 Units—The values stated in SI units are to be regarded
fications C787 and C996, has to meet different requirements:
as the standard. No other units of measurement are included in
one set of requirements being safety, health physics, and
this standard.
criticality and the other set being chemical, physical, and
1.4 This standard does not purport to address all of the
isotopic. To ensure the UF is in compliance with all
6
safety concerns, if any, associated with its use. It is the
requirements, sampling and analysis shall be performed.
responsibility of the user of this standard to establish appro-
Therefore, packaging may have a significant impact on the
priate safety, health, and environmental practices and deter-
quality of UF .
6
mine the applicability of regulatory limitations prior to use.
4.2 After sampling, the bottle will contain residues.There is
1.5 This international standard was developed in accor-
contamination because of the equipment, other contamination
dance with internationally recognized principles on standard-
caused by nonvolatile elements, and isotopic contamination as
ization established in the Decision on Principles for the
a result of UF hydrolysis.
Development of International Standards, Guides and Recom- 6
mendations issued by the World Trade Organization Technical
4.3 Cleaning shall be efficient. Special emphasis should be
Barriers to Trade (TBT) Committee.
given to decontaminate the bottles without leaving any trace of
cleaning products, make the bottles inert in UF medium
6
2. Referenced Documents
(passivation bottle), and minimize waste. The cleaning process
2
should be easy, safe, and environmentally friendly.
2.1 ASTM Standards:
C787 Specification for Uranium Hexafluoride for Enrich-
4.4 This practice describes different protocols for cleaning
ment
bottles by gas and liquid.
C859 Terminology Relating to Nuclear Materials
C996 Specification for Uranium Hexafluoride Enriched to
5. Description of Sample Bottles
235
Less Than 5 % U
5.1 Abottleiscomposedofacylinder,adaptors,andavalve
3
2.2 ANSI Standard:
(see Fig. 1).
N14.1 Nuclear Materials—Uranium Hexafluoride—
5.2 Adaptorsarebrazedorweldedonthevalveandscrewed
Packaging for Transport
on the cylinder.
5.3 Bottles and valves are made from nickel or nickel-
copper alloy (for example, Monel).
1
This practice is under the jurisdiction of ASTM Committee C26 on Nuclear
Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel and
5.4 The design pressure and temperature are indicated in
Fertile Material Specifications.
ANSI N14.1.
Current edition approved Oct. 1, 2021. Published October 2021. Originally
approved in 2016. Last previous edition approved in 2016 as C1838 – 16. DOI:
10.1520/C1838-16R21.
6. Reagents
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
6.1 Purity of Reagents—Reagent-grade chemicals shall be
Standards volume information, refer to the standard’s Document Summary page on
used in all tests. Unless otherwise indicated, it is intended that
the ASTM website.
3
all reagents conform to the specifications of the Committee on
Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
4th Floor, New York, NY 10036, http://www.ansi.org. Analytical Reagents of the American Chemical Society where
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C1838 − 16 (2021)
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
6.5 Phosphoric Acid:
6.5.1 Composition—Phosphoric acid is used at about 1
-1
mol.L .
6.5.2 Hazards—Corrosive reagent and it causes b
...

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4.1 The process of selection, training and qualification of personnel involved with NDA measurements is one of the quality assurance elements for an overall quality NDA measurement program.  
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ASTM C1703-18(2023)(Practice)
Standard Practice for Sampling of Gaseous Uranium Hexafluoride for Enrichment

SIGNIFICANCE AND USE
5.1 Uranium hexafluoride is normally produced and handled in large (typically 1 to 14-ton) quantities and must, therefore, be characterized by reference to representative samples (see ISO 7195). The samples are used to determine compliance with the applicable commercial specification C787. The quantities involved, physical properties, chemical reactivity, and hazardous nature of UF6 are such that for representative sampling, specially designed equipment must be used and operated in accordance with the most carefully controlled and stringent procedures. This practice can be used by UF6 converters to review the effectiveness of existing procedures or as a guide to the design of equipment and procedures for future use.  
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1.1 This practice covers methods for withdrawing representative sample(s) of uranium hexafluoride (UF6) during a transfer occurring in the gas phase. Such transfer in the gas phase can take place during the filling of a cylinder during a continuous production process, for example the distillation column in a conversion facility. Such sample(s) may be used for determining compliance with the applicable commercial specification, for example Specification C787.  
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ASTM C1108-23(Test Method)
Standard Test Method for Plutonium by Controlled-Potential Coulometry

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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.  
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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.
SCOPE
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 C1455-14(2023)(Test Method)
Standard Test Method for Nondestructive Assay of Special Nuclear Material Holdup Using Gamma-Ray Spectroscopic Methods

SIGNIFICANCE AND USE
5.1 Measurement results from this test method assists in demonstrating regulatory compliance in such areas as safeguards SNM inventory control, criticality control, waste disposal, and decontamination and decommissioning (D&D). This test method can apply to the measurement of holdup in process equipment or discrete items whose gamma-ray absorption properties may be measured or estimated. This method may be adequate to accurately measure items with complex distributions of radioactive and attenuating material, however, the results are subject to larger measurement uncertainties than measurements of less complex distributions of radioactive material.  
5.2 Scan—A scan is used to provide a qualitative indication of the extent, location, and the relative quantity of holdup. It can be used to plan or supplement the quantitative measurements.  
5.3 Nuclide Mapping—Nuclide mapping measures the relative isotopic composition of the holdup at specific locations. It can also be used to detect the presence of radionuclides that emit radiation which could interfere with the assay. Nuclide mapping is best performed using a high resolution detector (such as HPGe) for best nuclide and interference detection. If the holdup is not isotopically homogeneous at the measurement location, that measured isotopic composition will not be a reliable estimate of the bulk isotopic composition.  
5.4 Quantitative Measurements—These measurements result in quantification of the mass of the measured nuclides in the holdup. They include all the corrections, such as attenuation, and descriptive information, such as isotopic composition, that are available  
5.4.1 High quality results require detailed knowledge of radiation sources and detectors, transmission of radiation, calibration, facility operations and error analysis. Judicious use of subject matter experts is required (Guide C1490).  
5.5 Holdup Monitoring—Periodic re-measurement of holdup at a defined point using the same technique and a...
SCOPE
1.1 This test method describes gamma-ray methods used to nondestructively measure the quantity of 235U or  239Pu present as holdup in nuclear facilities. Holdup may occur in any facility where nuclear material is processed, in process equipment, in exhaust ventilation systems and in building walls and floors.  
1.2 This test method includes information useful for management, planning, selection of equipment, consideration of interferences, measurement program definition, and the utilization of resources  (1, 2, 3, 4) .2  
1.3 The measurement of nuclear material hold up in process equipment requires a scientific knowledge of radiation sources and detectors, transmission of radiation, calibration, facility operations and uncertainty analysis. It is subject to the constraints of the facility, management, budget, and schedule; plus health and safety requirements. The measurement process includes defining measurement uncertainties and is sensitive to the form and distribution of the material, various backgrounds, and interferences. The work includes investigation of material distributions within a facility, which could include potentially large holdup surface areas. Nuclear material held up in pipes, ductwork, gloveboxes, and heavy equipment, is usually distributed in a diffuse and irregular manner. It is difficult to define the measurement geometry, to identify the form of the material, and to measure it without interference from adjacent sources of radiation.  
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...

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