1、Designation: C 788 03Standard 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 of last revision.
2、A number in parentheses indicates the year of last reapproval. Asuperscript epsilon (e) 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 %235Uintended for subsequent
3、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 diversity of manufactur-i
4、ng 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 the uranyl nitrat
5、e 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 reprocessed andcommercial s
6、tandard 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 criticality accid
7、ents,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. Government Document is t
8、heCode of Federal Regulations (latest edition), Title 10, Part 50.21.5 This standard does not purport to address all of thesafety concerns, if any, associated with its use. It is theresponsibility of the user of this standard to establish appro-priate safety and health practices and determine the ap
9、plica-bility of regulatory limitations prior to use.2. Referenced Documents2.1 ASTM Standards:C 787 Specification for Uranium Hexafluoride for Enrich-ment3C 799 Test Methods for Chemical, Mass Spectrometric,Spectrochemical, Nuclear, and Radiochemical Analysis ofNuclear-Grade Uranyl Nitrate Solutions
10、3C 859 Terminology Relating to Nuclear Materials3C 996 Specification for Uranium Hexafluoride Enriched toLess Than 5 %235U3C 1233 Practice for Determining Equivalent Boron Con-tents of Nuclear Materials3C 1295 Test Method for Gamma Energy Emission fromFission Products in Uranium Hexafluoride and Ura
11、nylNitrate Solution32.2 ANSI Standard:4ANSI/ASME NQA-1 Quality Assurance, Requirements forNuclear Facility Applications2.3 U.S. Government Document:Code of Federal Regulations, Title 10, (Energy), Part 50,Domestic Licensing of Production and Utilization Facili-ties3. Terminology3.1 Definitions of Te
12、rms 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 nitraterefers to ura-nyl nitrate made from unirradiated uranium. However, it isrecognized that some contamination with reprocessed uraniummay
13、occur during routine processing; this is acceptable, pro-vided that the product meets the specification for commercialstandard uranyl nitrate as defined in 4.2.3.1.1.2 reprocessed uranyl nitraterefers to any uranylnitrate made from uranium that has been exposed in a neutronirradiation facility and s
14、ubsequently chemically separated fromthe fission products and transuranic isotopes so generated. Thelimits given in this specification are intended to be typical ofreprocessed spent fuel having achieved burn-up levels of up to1This specification is under the jurisdiction of ASTM Committee C26 onNucl
15、ear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fueland Fertile Material Specifications.Current edition approved July 10, 2003. Published August 2003. Originallypublished as C 788 76. Last previous edition C 788 98.2Available from the Superintendent of Documents, U.S. Gover
16、nment PrintingOffice, Washington, DC 20402.3Annual Book of ASTM Standards, Vol 12.01.4Available from the American National Standards Institute, 11 W. 42nd St., 13thFloor, New York, NY 10036.1Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United St
17、ates.50 000 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 accommodate differentfuel histories.4. Radionuclide Content4.1 The235U content shall be reported as g/100 g U.4.2 For commercial st
18、andard uranyl nitrate, the concentra-tion of99Tc,232U,234U and236U shall be as specified inSpecifications C 787 or C 996, as appropriate, unless otherwiseagreed upon between purchaser and manufacturer. For99Tc and232U, the specific isotopic measuremetns required by theappropriate specifiation may be
19、 waived, provided that themanufacturer can demonstrate compliance, for instance,through the manufacturers quality assurance records.4.3 For reprocessed uranyl nitrate, the concentrations of99Tc,232U,234U and236U shall be as specified in SpecificationsC 787 or C 996, as appropriate, unless otherwise
20、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 gamma energy per disintegration arising fromfission products shall not exceed 3 3 105MeV-Bq/ Kg U. Theradionuclides to be deter
21、mined 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 due to transuranic alphaemitters shall be 250 Bq/g U (15 000 dpm/g U); the maximumalpha activity due to neptunium shall be 125 Bq
22、/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 shall apply unless otherwiseagreed upon between purchaser and manufacturer.5. Chemical Requirements5.1 The limits of uranium con
23、centration and the free nitricacid concentration of the aqueous uranyl nitrate solution shallbe agreed between purchaser and manufacturer.5.2 The uranyl nitrate solution shall contain no more than0.5 volume% of entrained organic materials.5.3 When the uranyl nitrate is intended as feed material forc
24、onversion 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 of concentrations of the following elements(which do not form volatile fluorides) shall not exceed 500g/g U:Aluminum Iron Silve
25、rBarium Lead SodiumBismuth Lithium StrontiumCadmium Magnesium ThoriumCalcium Manganese TinCopper Nickel ZincPotassium Zirconium5.4 When the uranyl nitrate is intended for direct conversionto an oxide (not through the hexafluoride), the followingclauses shall apply:5.4.1 The impurity limit of each el
26、ement 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 boron content (EBC) shall notexceed 4.0 g/g U. The total EBC shall be determined perPractice C 1233. For fast reactor use the l
27、imitation 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” value shall be used for any further calculationsinvolving the concentration of this element.6. Sampling6.1 A representative samp
28、le of sufficient size to perform thetests prescribed herein shall be taken. Because of the potentialTABLE 1 Impurity Limits in Uranyl Nitrate for Conversion toUranium HexafluorideElement MaximumConcentrationLimit, g/gUAntimony 1Arsenic 3Boron 1Bromine 5Chlorine 100Chromium 10Fluorine 25Molybdenum 1.
29、4Niobium 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 200Ir
30、on 200Lead 200Manganese 200Molybdenum 200Nickel 150Phosphorus 200Silicon 200Tantalum 200Thorium 10Tin 200Titanium 200Tungsten 200Vanadium 200Zinc 200C788032presence of several liquid phases (organic materials), carefulattention should be taken when sampling and subsampling.6.2 Because of the potenti
31、al presence of several liquidphases (organic materials) in uranyl nitrate solution, carefulattention should be taken when sampling and subsampling.6.3 Uranyl nitrate crystals are hygroscopic and retain suffi-cient water after exposure to a moist atmosphere to causedetectable errors. Sample, weigh, a
32、nd handle the sample underconditions that will ensure that the sample is representative ofthe lot. Analytical confirmation of sampling plans shall bedocumented as part of the manufacturers quality assuranceand nuclear materials control and accountability programs.6.4 All samples shall be clearly ide
33、ntified, including themanufacturers lot number.6.5 All containers used for a lot shall be positively identifiedas containing material from a particular homogeneous lot.7. Methods of Chemical and Isotopic Analysis7.1 Methods C 799, or demonstrated equivalent, shall beused as mutually agreed between t
34、he purchaser and manufac-turers. Methods not currently provided by Methods C 799 shallbe as mutually agreed between purchaser and manufacturers.8. Quality Assurance8.1 Quality assurance requirements shall be agreed uponbetween the purchaser and manufacturer when specified in thepurchase order. Code
35、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 nitrateASTM International takes no position respecting the validity of any patent rights asserted in connection with any item mentionedin this
36、 standard. Users of this standard are expressly advised that determination of the validity of any such patent rights, and the riskof infringement of such rights, are entirely their own responsibility.This standard is subject to revision at any time by the responsible technical committee and must be
37、reviewed every five years andif not revised, either reapproved or withdrawn. Your comments are invited either for revision of this standard or for additional standardsand should be addressed to ASTM International Headquarters. Your comments will receive careful consideration at a meeting of therespo
38、nsible technical committee, which you may attend. If you feel that your comments have not received a fair hearing you shouldmake your views known to the ASTM Committee 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).C788033
