1、Designation: C 788 03 (Reapproved 2009)Standard Specification forNuclear-Grade Uranyl Nitrate Solution or Crystals1This standard is issued under the fixed designation C 788; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year
2、of last revision. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon () indicates an editorial change since the last revision or reapproval.1. Scope1.1 This specification applies to nuclear-grade aqueousuranyl nitrate solution or crystals not exceeding 5 %235Uintende
3、d for subsequent manufacture into either UF6(for feedto an enrichment plant) or direct conversion to uranium oxide(for use in reactors).1.2 This specification is intended to provide the nuclearindustry with a general standard for aqueous uranyl nitratesolution or crystals. It recognizes the diversit
4、y of manufactur-ing methods and the processes to which it is subsequently to besubjected. It is therefore anticipated that it may be necessary toinclude supplementary specification limits by agreement be-tween purchaser and manufacturer. Different limits are appro-priate depending on whether or not
5、the uranyl nitrate is to beconverted to UF6for subsequent processing.1.3 The purpose of this specification is: (a) to define theimpurity and uranium isotope limits for commercial standarduranyl nitrate, and (b) to define additional limits for repro-cessed uranyl nitrate (or any mixture of reprocesse
6、d andcommercial standard uranyl nitrate). For such uranyl nitrates,special provisions may need to be made to ensure that no extrahazard arises to the employees, the process equipment, or theenvironment.1.4 The scope of this specification does not comprehen-sively cover all provisions for preventing
7、criticality accidents,for health and safety, or for shipping. Observance of thisstandard does not relieve the user of the obligation to conformto all international, federal, state and local regulations forprocessing, shipping, or any other way of using the uranylnitrate. An example of a U.S. Governm
8、ent Document is theCode of Federal Regulations, Title 10, Part 50 (latest edition).1.5 The values stated in SI units are to be regarded asstandard. No other units of measurement are included in thisstandard.1.6 This standard does not purport to address all of thesafety concerns, if any, associated w
9、ith its use. It is theresponsibility of the user of this standard to establish appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.2. Referenced Documents2.1 ASTM Standards:2C 787 Specification for Uranium Hexafluoride for Enrich-mentC 799
10、 Test Methods for Chemical, Mass Spectrometric,Spectrochemical, Nuclear, and Radiochemical Analysis ofNuclear-Grade Uranyl Nitrate SolutionsC 859 Terminology Relating to Nuclear MaterialsC 996 Specification for Uranium Hexafluoride Enriched toLess Than 5 %235UC 1233 Practice for Determining Equivale
11、nt Boron Con-tents of Nuclear MaterialsC 1295 Test Method for Gamma Energy Emission fromFission Products in Uranium Hexafluoride and UranylNitrate Solution2.2 ANSI Standard:3ANSI/ASME NQA-1 Quality Assurance, Requirements forNuclear Facility Applications2.3 U.S. Government Document:4Code of Federal
12、Regulations, Title 10, (Energy), Part 50,Domestic Licensing of Production and Utilization Facili-ties3. Terminology3.1 Definitions of Terms Specific to This Standard:3.1.1 Terms shall be defined in accordance with Terminol-ogy C 859, except for the following:3.1.1.1 commercial standard uranyl nitrat
13、erefers to ura-nyl nitrate made from unirradiated uranium. However, it isrecognized that some contamination with reprocessed uraniummay occur during routine processing; this is acceptable, pro-vided that the product meets the specification for commercialstandard uranyl nitrate as defined in 4.2.3.1.
14、1.2 reprocessed uranyl nitraterefers to any uranylnitrate made from uranium that has been exposed in a neutron1This specification is under the jurisdiction of ASTM Committee C26 onNuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fueland Fertile Material Specifications.Cu
15、rrent edition approved June 1, 2009. Published July 2009. Originally approvedin 1976. Last previous edition approved in 2003 as C 788 03.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume i
16、nformation, refer to the standards Document Summary page onthe ASTM website.3Available from American National Standards Institute (ANSI), 25 W. 43rd St.,4th Floor, New York, NY 10036, http:/www.ansi.org.4Available from U.S. Government Printing Office Superintendent of Documents,732 N. Capitol St., N
17、W, Mail Stop: SDE, Washington, DC 20401, http:/www.access.gpo.gov.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.irradiation facility and subsequently chemically separated fromthe fission products and transuranic isotopes so generat
18、ed. Thelimits given in this specification are intended to be typical ofreprocessed spent fuel having achieved burn-up levels of up to50 000 megawatt day per ton of uranium in light water reactorsand cooling for 10 years after discharge. It is recognized thatdifferent values would be necessary to acc
19、ommodate differentfuel histories.4. Radionuclide Content4.1 The235U content shall be reported as g/100 g U.4.2 For commercial standard uranyl nitrate, the concentra-tion of99Tc,232U,234U and236U shall be as specified inSpecifications C 787 or C 996, as appropriate, unless otherwiseagreed upon betwee
20、n purchaser and manufacturer. For99Tc and232U, the specific isotopic measuremetns required by theappropriate specifiation may be waived, provided that themanufacturer can demonstrate compliance, for instance,through the manufacturers quality assurance records.4.3 For reprocessed uranyl nitrate, the
21、concentrations of99Tc,232U,234U and236U shall be as specified in SpecificationsC 787 or C 996, as appropriate, unless otherwise agreedbetween purchaser and manufacturer.4.4 For reprocessed uranyl nitrate, the total of the productsof each specific mean gamma decay rate multiplied by eachspecific mean
22、 gamma energy per disintegration arising fromfission products shall not exceed 3 3 105MeV-Bq/ Kg U. Theradionuclides to be determined by the gamma spectrometermethod of Methods C 799, C 1295, or equivalent.4.5 For reprocessed uranyl nitrate that is to be converted toUF6, the maximum alpha activity d
23、ue to transuranic alphaemitters shall be 250 Bq/g U (15 000 dpm/g U); the maximumalpha activity due to neptunium shall be 125 Bq/g U (7500dpm/g U). For reprocessed uranyl nitrate that is to be converteddirectly into UO2fuel, the transuranic alpha emitter specifica-tion limits of Specification C 996
24、shall apply unless otherwiseagreed upon between purchaser and manufacturer.5. Chemical Requirements5.1 The limits of uranium concentration and the free nitricacid concentration of the aqueous uranyl nitrate solution shallbe agreed between purchaser and manufacturer.5.2 The uranyl nitrate solution sh
25、all contain no more than0.5 volume% of entrained organic materials.5.3 When the uranyl nitrate is intended as feed material forconversion to uranium hexafluoride, the following shall apply:5.3.1 The impurity limit of each element listed in Table 1shall not exceed its designated maximum.5.3.2 The sum
26、 of concentrations of the following elements(which do not form volatile fluorides) shall not exceed 500g/g U:Aluminum Iron SilverBarium Lead SodiumBismuth Lithium StrontiumCadmium Magnesium ThoriumCalcium Manganese TinCopper Nickel ZincPotassium Zirconium5.4 When the uranyl nitrate is intended for d
27、irect conversionto an oxide (not through the hexafluoride), the followingclauses shall apply:5.4.1 The impurity limit of each element listed in Table 2shall not exceed its designated maximum. The total of allelements listed in this table shall not exceed 1500 g/g ofuranium.5.4.2 The total equivalent
28、 boron content (EBC) shall notexceed 4.0 g/g U. The total EBC shall be determined perPractice C 1233. For fast reactor use the limitation on EBCdoes not apply.5.5 If the concentrations of any of the elements used in thecalculations in 5.3 and 5.4 are reported as a “less than” value,this “less than”
29、value shall be used for any further calculationsinvolving the concentration of this element.TABLE 1 Impurity Limits in Uranyl Nitrate for Conversion toUranium HexafluorideElement MaximumConcentrationLimit, g/gUAntimony 1Arsenic 3Boron 1Bromine 5Chlorine 100Chromium 10Fluorine 25Molybdenum 1.4Niobium
30、 1Phosphorus 50Ruthenium 1Silicon 100Sulphur 400Tantalum 1Titanium 1Tungsten 1.4Vanadium 1.4TABLE 2 Impurity Limits in Uranyl Nitrate for Direct Conversionto OxideElementMaximumConcentrationLimit,g/g UAluminum 150Calcium + Magnesium 150Chlorine + Fluorine 350Chromium 150Cobalt 80Copper 200Iron 200Le
31、ad 200Manganese 200Molybdenum 200Nickel 150Phosphorus 200Silicon 200Tantalum 200Thorium 10Tin 200Titanium 200Tungsten 200Vanadium 200Zinc 200C 788 03 (2009)26. Sampling6.1 A representative sample of sufficient size to perform thetests prescribed herein shall be taken. Because of the potentialpresenc
32、e of several liquid phases (organic materials), carefulattention should be taken when sampling and subsampling.6.2 Because of the potential presence of several liquidphases (organic materials) in uranyl nitrate solution, carefulattention should be taken when sampling and subsampling.6.3 Uranyl nitra
33、te crystals are hygroscopic and retain suffi-cient water after exposure to a moist atmosphere to causedetectable errors. Sample, weigh, and handle the sample underconditions that will ensure that the sample is representative ofthe lot. Analytical confirmation of sampling plans shall bedocumented as
34、part of the manufacturers quality assuranceand nuclear materials control and accountability programs.6.4 All samples shall be clearly identified, including themanufacturers lot number.6.5 All containers used for a lot shall be positively identifiedas containing material from a particular homogeneous
35、 lot.7. Methods of Chemical and Isotopic Analysis7.1 Methods C 799, or demonstrated equivalent, shall beused as mutually agreed between the purchaser and manufac-turers. Methods not currently provided by Methods C 799 shallbe as mutually agreed between purchaser and manufacturers.8. Quality Assuranc
36、e8.1 Quality assurance requirements shall be agreed uponbetween the purchaser and manufacturer when specified in thepurchase order. Code of Federal Regulations, Title 10, Part 50,Appendix B and ASME NQA-1 are referenced as guides.9. Keywords9.1 uranium isotope limits; uranium solutions; uranyl nitra
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40、ttee on Standards, at the address shown below.This standard is copyrighted by ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959,United States. Individual reprints (single or multiple copies) of this standard may be obtained by contacting ASTM at the aboveaddress or at 610-832-9585 (phone), 610-832-9555 (fax), or serviceastm.org (e-mail); or through the ASTM website(www.astm.org).C 788 03 (2009)3
