Standard Specification for Nuclear-Grade Uranyl Nitrate Solution or Crystals

ABSTRACT
This specification applies to nuclear-grade aqueous uranyl nitrate solution or crystals not exceeding 5% 235U intended for subsequent manufacture into either UF6 or direct conversion to uranium oxide. This specification is intended to provide the nuclear industry with a general standard for aqueous uranyl nitrate solution or crystals. The purpose of this specification is: to define the impurity and uranium isotope limits for commercial standard uranyl nitrate, and to define additional limits for reprocessed uranyl nitrate (or any mixture of reprocessed and commercial standard uranyl nitrate).
SCOPE
1.1 This specification applies to nuclear-grade aqueous uranyl nitrate solution or crystals not exceeding 5 %  235U intended for subsequent manufacture into either UF6  (for feed to an enrichment plant) or direct conversion to uranium oxide (for use in reactors).
1.2 This specification is intended to provide the nuclear industry with a general standard for aqueous uranyl nitrate solution or crystals. It recognizes the diversity of manufacturing methods and the processes to which it is subsequently to be subjected. It is therefore anticipated that it may be necessary to include supplementary specification limits by agreement between purchaser and manufacturer. Different limits are appropriate depending on whether or not the uranyl nitrate is to be converted to UF6  for subsequent processing.
1.3 The purpose of this specification is: (a) to define the impurity and uranium isotope limits for commercial standard uranyl nitrate, and (b) to define additional limits for reprocessed uranyl nitrate (or any mixture of reprocessed and commercial standard uranyl nitrate). For such uranyl nitrates, special provisions may need to be made to ensure that no extra hazard arises to the employees, the process equipment, or the environment.
1.4 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents, for health and safety, or for shipping. Observance of this standard does not relieve the user of the obligation to conform to all international, federal, state and local regulations for processing, shipping, or any other way of using the uranyl nitrate. An example of a U.S. Government Document is the Code of Federal Regulations, Title 10, Part 50 (latest edition).
1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.6 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.

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Publication Date
31-May-2009
Current Stage
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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:C788 −03(Reapproved2009)
Standard Specification for
Nuclear-Grade Uranyl Nitrate Solution or Crystals
This standard is issued under the fixed designation C788; 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 responsibility of the user of this standard to establish appro-
priate safety and health practices and determine the applica-
1.1 This specification applies to nuclear-grade aqueous
235 bility of regulatory limitations prior to use.
uranyl nitrate solution or crystals not exceeding 5% U
intended for subsequent manufacture into either UF (for feed
2. Referenced Documents
to an enrichment plant) or direct conversion to uranium oxide
(for use in reactors). 2.1 ASTM Standards:
C787Specification for Uranium Hexafluoride for Enrich-
1.2 This specification is intended to provide the nuclear
ment
industry with a general standard for aqueous uranyl nitrate
C799Test Methods for Chemical, Mass Spectrometric,
solution or crystals. It recognizes the diversity of manufactur-
Spectrochemical,Nuclear,andRadiochemicalAnalysisof
ingmethodsandtheprocessestowhichitissubsequentlytobe
Nuclear-Grade Uranyl Nitrate Solutions
subjected.Itisthereforeanticipatedthatitmaybenecessaryto
C859Terminology Relating to Nuclear Materials
include supplementary specification limits by agreement be-
C996Specification for Uranium Hexafluoride Enriched to
tween purchaser and manufacturer. Different limits are appro-
Less Than 5 % U
priate depending on whether or not the uranyl nitrate is to be
C1233Practice for Determining Equivalent Boron Contents
converted to UF for subsequent processing.
of Nuclear Materials
1.3 The purpose of this specification is: (a) to define the
C1295Test Method for Gamma Energy Emission from
impurity and uranium isotope limits for commercial standard
Fission Products in Uranium Hexafluoride and Uranyl
uranyl nitrate, and (b) to define additional limits for repro-
Nitrate Solution
cessed uranyl nitrate (or any mixture of reprocessed and
2.2 ANSI Standard:
commercial standard uranyl nitrate). For such uranyl nitrates,
ANSI/ASME NQA-1Quality Assurance, Requirements for
special provisions may need to be made to ensure that no extra
Nuclear Facility Applications
hazard arises to the employees, the process equipment, or the
2.3 U.S. Government Document:
environment.
Code of Federal Regulations, Title 10,(Energy), Part 50,
1.4 The scope of this specification does not comprehen-
Domestic Licensing of Production and Utilization Facili-
sively cover all provisions for preventing criticality accidents,
ties
for health and safety, or for shipping. Observance of this
standard does not relieve the user of the obligation to conform
3. Terminology
to all international, federal, state and local regulations for
3.1 Definitions of Terms Specific to This Standard:
processing, shipping, or any other way of using the uranyl
3.1.1 Terms shall be defined in accordance with Terminol-
nitrate. An example of a U.S. Government Document is the
ogy C859, except for the following:
Code of Federal Regulations, Title 10, Part 50 (latest edition).
3.1.1.1 commercial standard uranyl nitrate—refers to ura-
1.5 The values stated in SI units are to be regarded as
nyl nitrate made from unirradiated uranium. However, it is
standard. No other units of measurement are included in this
recognized that some contamination with reprocessed uranium
standard.
1.6 This standard does not purport to address all of the
safety concerns, if any, associated with its use. It is the 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
This specification is under the jurisdiction of ASTM Committee C26 on the ASTM website.
NuclearFuelCycleandisthedirectresponsibilityofSubcommitteeC26.02onFuel Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
and Fertile Material Specifications. 4th Floor, New York, NY 10036, http://www.ansi.org.
CurrenteditionapprovedJune1,2009.PublishedJuly2009.Originallyapproved AvailablefromU.S.GovernmentPrintingOfficeSuperintendentofDocuments,
in 1976. Last previous edition approved in 2003 as C788–03. DOI: 10.1520/ 732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http://
C0788-03R09. www.access.gpo.gov.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
C788−03(2009)
TABLE 1 Impurity Limits in Uranyl Nitrate for Conversion to
may occur during routine processing; this is acceptable, pro-
Uranium Hexafluoride
vided that the product meets the specification for commercial
Element Maximum Concentration Limit,
standard uranyl nitrate as defined in 4.2.
µg/g U
3.1.1.2 reprocessed uranyl nitrate—refers to any uranyl
Antimony 1
nitrate made from uranium that has been exposed in a neutron
Arsenic 3
Boron 1
irradiationfacilityandsubsequentlychemicallyseparatedfrom
Bromine 5
the fission products and transuranic isotopes so generated.The
Chlorine 100
limits given in this specification are intended to be typical of Chromium 10
Fluorine 25
reprocessed spent fuel having achieved burn-up levels of up to
Molybdenum 1.4
50000megawattdaypertonofuraniuminlightwaterreactors
Niobium 1
and cooling for 10 years after discharge. It is recognized that Phosphorus 50
Ruthenium 1
different values would be necessary to accommodate different
Silicon 100
fuel histories.
Sulphur 400
Tantalum 1
Titanium 1
4. Radionuclide Content
Tungsten 1.4
Vanadium 1.4
4.1 The U content shall be reported as g/100 g U.
4.2 For commercial standard uranyl nitrate, the concentra-
99 232 234 236
tion of Tc, U, U and U shall be as specified in
Specifications C787 or C996, as appropriate, unless otherwise
agreeduponbetweenpurchaserandmanufacturer.For Tcand
Aluminu
...


This document is not anASTM standard and is intended only to provide the user of anASTM 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:C788–98 Designation: C 788 – 03 (Reapproved 2009)
Standard Specification for
Nuclear-Grade Uranyl Nitrate SolutionNuclear-Grade Uranyl
Nitrate Solution or Crystals
This standard is issued under the fixed designation C 788; 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 specification applies to nuclear-grade aqueous uranyl nitrate solution or crystals not exceeding 5 % U intended for
subsequent manufacture into either UF (for feed to an enrichment plant) or direct conversion to uranium oxide (for use in
reactors).
1.2 This specification is intended to provide the nuclear industry with a general standard for aqueous uranyl nitrate solution or
crystals. It recognizes the diversity of manufacturing methods and the processes to which it is subsequently to be subjected. It is
therefore anticipated that it may be necessary to include supplementary specification limits by agreement between purchaser and
manufacturer. Different limits are appropriate depending on whether or not the uranyl nitrate is to be converted to UF for
subsequent processing.
1.3 The purpose of this specification is: (a) to define the impurity and uranium isotope limits for commercial standard uranyl
nitrate, and (b) to define additional limits for reprocessed uranyl nitrate (or any mixture of reprocessed and commercial standard
uranyl nitrate). For such uranyl nitrates, special provisions may need to be made to ensure that no extra hazard arises to the
employees, the process equipment, or the environment.
1.4 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents, for health
and safety, or for shipping. Observance of this standard does not relieve the user of the obligation to conform to all international,
federal, state and local regulations for processing, shipping, or any other way of using the uranyl nitrate. An example of a U.S.
Government Document is the Code of Federal Regulations (latest edition), Regulations, Title 10, Part 50. 50 (latest edition).
1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.6 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
2.1 ASTM Standards:
C 787 Specification for Uranium Hexafluoride for Enrichment
C 799 Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-
Grade Uranyl Nitrate Solutions
C 859 Terminology Relating to Nuclear Materials
C 996 Specification for Uranium Hexafluoride Enriched to Less Than 5 % U
C 1233 Practice for Determining Equivalent Boron Contents of Nuclear Materials
C 1295 Test Method for Gamma Energy Emission from Fission Products in Uranium Hexafluoride and Uranyl Nitrate Solution
2.2 ANSI Standard:
ANSI/ASME NQA-1Quality Assurance Program, Requirements for Nuclear Facilities Quality Assurance, Requirements for
Nuclear Facility Applications
2.3 U.S. Government Document:
This specification is under the jurisdiction of ASTM Committee C-26 C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel and
Fertile Material Specifications.
Current edition approved July 10, 1998. Published November 1998. Originally published as C788–76. Last previous edition C788–93.
Current edition approved June 1, 2009. Published July 2009. Originally approved in 1976. Last previous edition approved in 2003 as C 788 – 03.
Available from the Superintendent of Documents, U.S. Government Printing Office, Washington, DC 20402.
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM 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.
Annual Book of ASTM Standards, Vol 12.01.
Available from American National Standards Institute (ANSI), 25 W. 43rd St., 4th Floor, New York, NY 10036, http://www.ansi.org.
Available from the American National Standards Institute, 11 W. 42nd St., 13th Floor, New York, NY 10036.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
C 788 – 03 (2009)
Code of Federal Regulations, Title 10, (Energy), Part 50, Domestic Licensing of Production and Utilization Facilities
2.4 Other Document:
Davies, B. S. J. and Tobias, A., A Summary of the Data Available in ENDF 1BFormat, CEGB Report RD/B/5095 N81
(November 1981)
3. Terminology
3.1 Definitions of Terms Specific to This Standard:
3.1.1 Terms shall be defined in accordance with Terminology C 859, except for the following:
3.1.1.1 commercial standard uranyl nitrate—referstouranylnitratemadefromunirradiateduranium.However,itisrecognized
that some contamination with reprocessed uranium may occur during routine processing; this is acceptable, provided that the
product meets the specification for commercial standard uranyl nitrate as defined in 4.2.
3.1.1.2 reprocessed uranyl nitrate —refers to any uranyl nitrate made from uranium that has been exposed in a neutron
irradiation facility and subsequently chemically separated from the fission products and transuranic isotopes so generated. The
limitsgiveninthisspecificationareintendedtobetypicalofreprocessedspentfuelhavingachievedburn-uplevelsofupto50 000
megawatt day per ton of uranium in light water reactors and cooling for 10 years after discharge. It is recognized that different
limitsvalues would be necessary to accommodate different fuel histories.
4. Radionuclide Content
4.1 The U content shall be reported as g/100 g U.
99 232 234 236
4.2 Forcommercialstandarduranylnitrate,theconcentrationof Tc, U, Uand UshallbeasspecifiedinSpecifications
C787 or C996, as appropriate, unless otherwise agreed upon between purchaser and manufacturer. U shall be as specified in
Specifications C 787 or C 996, as appropriate, unless otherwise agreed upon between purchaser and manufacturer. For Tc and
232 U, the specific isotopic measuremetns required by the appropriate specifiation may be waived, provided that the manufacturer
can demonstrate compliance, for instance, through the manufacturer’s quality assurance records.
99 232 234 236
4.3 For reprocessed uranyl nitrate, the concentrations of Tc, U, U and U shall be as specified in Specifications C 787
or C996 or C 996, as appropriate, unless otherwise agreed between purchaser and manufacturer.
4.4 For reprocessed uranyl nitrate, the total of the products of each specific mean gamma decay rate multiplied by each specific
mean gamma energy per disintegration arising from fission products shall not exceed 3 3 10 MeV-Bq/dMeV-Bq/ Kg U. The
radionuclides to be determined by the gamma spectrometer method of Methods C 799, C 1295, or equivalent.
The presence of any other detectable gamma emitting fission product isotope shall
...

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