ASTM C788-2003(2015) Standard Specification for Nuclear-Grade Uranyl Nitrate Solution or Crystals《核纯级硝酸铀酰溶液或晶体的标准规格》.pdf

1、Designation: C788 03 (Reapproved 2015)Standard Specification forNuclear-Grade Uranyl Nitrate Solution or Crystals1This standard is issued under the fixed designation C788; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of

2、 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 %235Uintended

3、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 diversity

4、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 th

5、e 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 reprocessed

6、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 cr

7、iticality 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. Governmen

8、t 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 wit

9、h 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:2C787 Specification for Uranium Hexafluoride for Enrich-mentC799 Tes

10、t Methods for Chemical, Mass Spectrometric,Spectrochemical, Nuclear, and RadiochemicalAnalysis ofNuclear-Grade Uranyl Nitrate SolutionsC859 Terminology Relating to Nuclear MaterialsC996 Specification for Uranium Hexafluoride Enriched toLess Than 5 %235UC1233 Practice for Determining Equivalent Boron

11、 Contentsof Nuclear MaterialsC1295 Test Method for Gamma Energy Emission fromFission and Decay Products in Uranium Hexafluoride andUranyl Nitrate Solution2.2 ANSI Standard:3ANSI/ASME NQA-1 Quality Assurance, Requirements forNuclear Facility Applications2.3 U.S. Government Document:4Code of Federal R

12、egulations, 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 C859, except for the following:3.1.1.1 commercial standard uranyl nitrater

13、efers to ura-nyl nitrate made from unirradiated uranium. However, it isrecognized that some contamination with reprocessed uranium1This specification is under the jurisdiction of ASTM Committee C26 onNuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fueland Fertile Materi

14、al Specifications.Current edition approved June 1, 2015. Published June 2015. Originallyapproved in 1976. Last previous edition approved in 2009 as C788 03 (2009).DOI: 10.1520/C0788-03R15.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at service

15、astm.org. For Annual Book of ASTMStandards volume information, 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 Offic

16、e Superintendent of Documents,732 N. Capitol St., NW, Mail Stop: SDE, Washington, DC 20401, http:/www.access.gpo.gov.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States1may occur during routine processing; this is acceptable, pro-vided th

17、at 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 subsequently chemically separated fromthe fission products and tra

18、nsuranic isotopes so generated. 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 valu

19、es 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 standard uranyl nitrate, the concentra-tion of99Tc,232U,234U and236U shall be as specified inSpecifications C787 or C996, as appropriate, unless o

20、therwiseagreed upon between purchaser and manufacturer. For99Tc and232U, the specific isotopic measurements required by theappropriate specification may be waived, provided that themanufacturer can demonstrate compliance, for instance,through the manufacturers quality assurance records.4.3 For repro

21、cessed uranyl nitrate, the concentrations of99Tc,232U,234U and236U shall be as specified in SpecificationsC787 or C996, as appropriate, unless otherwise agreed betweenpurchaser and manufacturer.4.4 For reprocessed uranyl nitrate, the total of the productsof each specific mean gamma decay rate multip

22、lied by eachspecific mean gamma energy per disintegration arising fromfission products shall not exceed 3 105MeV-Bq/ Kg U. Theradionuclides to be determined by the gamma spectrometermethod of Methods C799, C1295, or equivalent.4.5 For reprocessed uranyl nitrate that is to be converted toUF6, the max

23、imum 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/g U (7500dpm/g U). For reprocessed uranyl nitrate that is to be converteddirectly into UO2fuel, the transuranic alpha emitter specifica-tion limits of

24、 Specification C996 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

25、 nitrate solution shall 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 m

26、aximum.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 SilverBarium Lead SodiumBismuth Lithium StrontiumCadmium Magnesium ThoriumCalcium Manganese TinCopper Nickel ZincPotassium Zirconium5.4 When the uranyl nitra

27、te is intended for direct 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

28、The total equivalent boron content (EBC) shall notexceed 4.0 g/g U. The total EBC shall be determined perPractice C1233. For fast reactor use the limitation on EBC doesnot apply.TABLE 1 Impurity Limits in Uranyl Nitrate for Conversion toUranium HexafluorideElement Maximum Concentration Limit,g/g UAn

29、timony 1Arsenic 3Boron 1Bromine 5Chlorine 100Chromium 10Fluorine 25Molybdenum 1.4Niobium 1Phosphorus 50Ruthenium 1Silicon 100Sulphur 400Tantalum 1Titanium 1Tungsten 1.4Vanadium 1.4TABLE 2 Impurity Limits in Uranyl Nitrate for Direct Conversionto OxideElementMaximum Concentration Limit,g/g UAluminum

30、150Calcium + Magnesium 150Chlorine + Fluorine 350Chromium 150Cobalt 80Copper 200Iron 200Lead 200Manganese 200Molybdenum 200Nickel 150Phosphorus 200Silicon 200Tantalum 200Thorium 10Tin 200Titanium 200Tungsten 200Vanadium 200Zinc 200C788 03 (2015)25.5 If the concentrations of any of the elements used

31、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 sample of sufficient size to perform thetests prescribed herein shall be taken. Because o

32、f the potentialpresence 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 subsam

33、pling.6.3 Uranyl nitrate 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

34、shall bedocumented as 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

35、particular homogeneous lot.7. Methods of Chemical and Isotopic Analysis7.1 Methods C799, or demonstrated equivalent, shall beused as mutually agreed between the purchaser and manufac-turers. Methods not currently provided by Methods C799 shallbe as mutually agreed between purchaser and manufacturers

36、.8. Quality Assurance8.1 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 sol

37、utions; uranyl nitrateASTM International takes no position respecting the validity of any patent rights asserted in connection with any item mentionedin this standard. Users of this standard are expressly advised that determination of the validity of any such patent rights, and the riskof infringeme

38、nt 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 reviewed every five years andif not revised, either reapproved or withdrawn. Your comments are invited either for revision of this standard or

39、for additional standardsand should be addressed to ASTM International Headquarters. Your comments will receive careful consideration at a meeting of theresponsible technical committee, which you may attend. If you feel that your comments have not received a fair hearing you shouldmake your views kno

40、wn 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 AST

41、M 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). Permission rights to photocopy the standard may also be secured from the Copyright Clearance Center, 222Rosewood Drive, Danvers, MA 01923, Tel: (978) 646-2600; http:/ 03 (2015)3