ASTM C757-2006 Standard Specification for Nuclear-Grade Plutonium Dioxide Powder Sinterable《核纯级可烧结的二氧化钚粉末的规格》.pdf

1、Designation: C 757 06Standard Specification forNuclear-Grade Plutonium Dioxide Powder, Sinterable1This standard is issued under the fixed designation C 757; 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.INTRODUCTIONThis specification is intended to provide the nuclear industry with a general standard for sinterableplutonium dioxide powder. It r

3、ecognizes the diversity of manufacturing methods by which plutoniumdioxide powders are produced, and the many special requirements for chemical and physicalcharacterization that may be imposed by the end use of the powder in a specific reactor system. It is,therefore, anticipated that the buyer may

4、supplement this specification with more stringent oradditional requirements for specific applications.1. Scope1.1 This specification covers nuclear grade plutonium diox-ide, sinterable powder obtained by the oxalate precipitationroute, calcined above 500C, or any other equivalent processacceptable t

5、o the buyer. Included is plutonium dioxide ofvarious isotopic compositions as normally prepared by in-reactor neutron irradiation of natural or slightly enricheduranium or by in-reactor neutron irradiation of recycled pluto-nium mixed with uranium.1.2 There is no discussion of or provision for preve

6、ntingcriticality incidents, nor are health and safety requirements, theavoidance of hazards, or shipping precautions and controlsdiscussed. Observance of this specification does not relieve theuser of the obligation to be aware of and conform to all nationaland local regulations on processing, shipp

7、ing, or using sourceor special nuclear materials. For examples in the U.S. Govern-ment, relevant documents are Code of Federal Regulations,Title 10 Nuclear Safety Guide, U.S. Atomic Energy Commis-sion Report TID-70162, and “Handbook of Nuclear Safety”, H.K. Clark, U.S. Atomic Energy Commission Repor

8、t, DP-5322.1.3 The PuO2shall be produced by a qualified process andin accordance with a quality assurance program approved bythe user.1.4 The values stated in SI units are to be regarded as thestandard.1.5 This standard does not purport to address all of thesafety concerns, if any, associated with i

9、ts 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:3C 697 Test Methods for Chemical, Mass Spectrometric, andSpectrochemica

10、l Analysis of Nuclear-Grade PlutoniumDioxide Powders and PelletsC 1233 Practice for Determining Equivalent Boron Con-tents of Nuclear MaterialsC 1295 Test Method for Gamma Energy Emission fromFission Products in Uranium Hexafluoride and UranylNitrate Solution2.2 ANSI Standard:ANSI/ASME NQA-1 Quality

11、 Assurance Requirements forNuclear Facility Applications42.3 U.S. Government Documents:Code of Federal Regulations, Title 10, Nuclear SafetyGuide, U.S. Atomic Energy Commission Report TID-70162“Handbook of Nuclear Safety,” Clark, H. K., U.S. AtomicEnergy Commission Report, DP-53222.4 ISO Standard:1T

12、his 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.Current edition approved July 1, 2006. Published July 2006. Originally approvedin 1974. Last previous edition appr

13、oved in 2002 as C 757 90 (2002).2Available from Superintendent of Documents, U.S. Government PrintingOffice, Washington, DC 20402.3For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume informat

14、ion, refer to the standards Document Summary page onthe ASTM website.4Available from 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 States.ISO 8300 Determ

15、ination of Pu Content in Plutonium Diox-ide (PuO2) of Nuclear Grade Quality, GravimetricMethod43. Isotopic Content3.1 Concentrations and homogeneity ranges of the pluto-nium isotopes shall be as specified by the buyer.3.2 The isotopic composition of the final product shall bedetermined by mass spect

16、rometry and shall be reported on aweight basis.4. Chemical Composition4.1 Plutonium ContentThe minimum Pu content shall be86.0 weight % as sampled on the date of sampling and 87.5weight % after heating4hto950C.4.2 Uranium ContentThe uranium content of the pluto-nium dioxide shall be measured and rep

17、orted on a plutoniumbasis.4.3 Americium ContentThe americium content shall bemeasured and reported on a plutonium basis. The maximumacceptable americium content shall be agreed upon betweenthe buyer and the seller.4.4 The dates of analyses of U, Th and Am shall berecorded.4.5 Impurity ContentThe imp

18、urity content shall not ex-ceed the individual element limit specified in Table 1. Totalnon-volatile oxide impurity content excluding Am shall notexceed 6000 g/g Pu. If an element analysis is reported as “lessthan” a given concentration, this “less than” value shall be usedin the determination of to

19、tal impurities.4.6 Equivalent Boron ContentFor thermal reactor use, thetotal equivalent boron content (EBC) shall not exceed 20.0g/g on a plutonium weight basis. For the purpose of EBCcalculation B, Gd, Eu, Dy, Sm, and Cd shall be included inaddition to elements listed in Table 1. The method of perf

20、orm-ing the calculation shall be as indicated in Practice C 1233. Forfast reactor use, the above limitation on EBC does not apply.4.7 Gamma ActivityThe gamma activity (Bq/g Pu) of thegamma emitting fission products whose isotopes have halflives of 30 days or greater shall be measured. The gammaradia

21、tion from fission products shall be less than 105MeVBq/g Pu.4.7.1 The list of nuclides and mean energies per disintegra-tion found in Test Method C 1295 are to be used in thecalculations.5. Physical Properties5.1 Cleanliness and WorkmanshipThe PuO2powder shallbe free of visible fragments of foreign

22、matter.5.2 Particle SizeAll the PuO2powder shall be capable ofpassing a 100 m sieve and 95 % of the powder by weight shallbe capable of passing a 44 m sieve.5.3 Surface AreaThe specific surface area shall not be lessthan 5 m2/g and not greater than 30 m2/g based on a Brunauer,Emmett, Teller (BET) ad

23、sorption method. See Notes 1 and 2.NOTE 1A specific surface area as low as 2 m2/g has been demon-strated to be acceptable when subsequently blended with other powder(s)of greater specific surface area. Therefore, powder with a specific surfacearea as low as 2 m2/g may be acceptable if agreed upon be

24、tween thesupplier and the user.NOTE 2Consideration should be given to the compatibility of pow-ders with widely different surface areas within the intended process.6. Sampling6.1 Plutonium oxide is hygroscopic and can absorb suffi-cient water during exposure to a moist atmosphere to causedetectable

25、analytical errors. Sampling, weighing of the sample,and handling the sample shall be done under atmosphericconditions that do not alter the moisture or impurity content ofthe sample.6.2 The necessary chemical and physical analyses shall beperformed on portions of a representative sample taken fromea

26、ch lot.6.2.1 A lot is defined as the quantity of material that isuniform in isotopic, chemical, and physical characteristics.6.2.2 Lots may be formed by blending the powder to ensurehomogeneity within each lot.6.2.3 The mixing of two or more lots shall require theestablishment of a new lot.6.3 Sampl

27、ing procedures, including the frequency and timeperiod for conducting analyses, shall be agreed upon betweenbuyer and seller in accordance with quality assurance require-ments.6.4 All sample containers shall be clearly identified by lotnumber and container number.6.5 The sample material shall be pac

28、kaged so that noforeign material is introduced into the powder during storage orshipment.7. Methods of Chemical and Isotopic Analysis7.1 The analytical chemistry methods used shall be asdescribed in Test Method C 697 or other methods agreed uponbetween buyer and seller. See, for example, ISO 8300 fo

29、rdetermination of Pu content in plutonium dioxide of nucleargrade quality.8. Quality Assurance8.1 Quality assurance requirements shall be agreed uponbetween buyer and seller. CFR Title 10, Part 50, Appendix 50and ANSI/ASME NQA-1 are referenced as guides.9. Rejection and Rehearing9.1 Rejection and ac

30、ceptance shall be by lot unless there isprior agreement to do otherwise between the buyer and seller.TABLE 1 Impurity Elements and Maximum Concentration LimitsElementMaximum Concentration Limitof Uranium, g/gPuBoron 3Cadmium 3CarbonA200Chlorine 300Chromium 200Fluorine 200Iron 300Gadolinium 3Nickel 1

31、00Nitride Nitrogen 200Thorium 200ASample may be heated prior to carbon analysis.C7570629.2 The buyer and seller shall agree to a third party as areferee in the event of a dispute in analytical results.10. Certification10.1 The seller shall test the sample described in theSampling section to ensure c

32、onformance of the oxide to therequirements of the Isotopic Content, Chemical Composition,and Physical Properties Sections.10.2 The seller shall provide the buyer documents certifyingthat the oxide meets all the requirements of the IsotopicContent, Chemical Composition, and Physical Properties Sec-ti

33、ons.10.3 The seller shall make available, as requested by thebuyer, records of all data from tests used to meet the require-ments in the Isotopic Content, Chemical Composition, andPhysical Properties Sections.11. Packaging and Package Marking11.1 Plutonium dioxide powder shall be packaged in sealedm

34、etal containers to prevent loss of material and undue con-tamination from air or the container materials. The exact sizeand method of packaging shall be as mutually agreed uponbetween the buyer and the seller, and in conformance with allapplicable regulations.11.2 Each metal container shall bear as

35、a minimum a labelon the lid and side with the following information:11.2.1 Sellers name,11.2.2 Lot number,11.2.3 Gross, tare, net oxide weights,11.2.4 Plutonium weight, and11.2.5 A unique container reference number.12. Keywords12.1 nuclear fuel; plutonium; plutonium dioxideASTM International takes n

36、o 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 infringement of such rights, are entirely their own respon

37、sibility.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 for additional standardsand should be addressed

38、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 known to the ASTM Committee on Standards, at the ad

39、dress 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).C757063