ASTM C1168-2008 Standard Practice for Preparation and Dissolution of Plutonium Materials for Analysis《分析用钚材料的制备和溶解的标准实施规程》.pdf
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1、Designation: C 1168 08Standard Practice forPreparation and Dissolution of Plutonium Materials forAnalysis1This standard is issued under the fixed designation C 1168; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of last
2、revision. 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 practice is a compilation of dissolution techniquesfor plutonium materials that are applicable to the test methodsuse
3、d for characterizing these materials. Dissolution treatmentsfor the major plutonium materials assayed for plutonium oranalyzed for other components are listed. Aliquants of thedissolved samples are dispensed on a weight basis when one ofthe analyses must be highly reliable, such as plutonium assay;o
4、therwise they are dispensed on a volume basis.1.2 The treatments, in order of presentation, are as follows:Procedure Title SectionDissolution of Plutonium Metal with Hydrochloric Acid 9.1Dissolution of Plutonium Metal with Sulfuric Acid 9.2Dissolution of Plutonium Oxide and Uranium-Plutonium MixedOx
5、ide by the Sealed-Reflux Technique9.3Dissolution of Plutonium Oxide and Uranium-Plutonium MixedOxides by Sodium Bisulfate Fusion9.4Dissolution of Uranium-Plutonium Mixed Oxides and Low-FiredPlutonium Oxide in Beakers9.51.3 The values stated in SI units are to be regarded asstandard.1.4 This standard
6、 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 applica-bility of regulatory limitations prior to use.2. Referenced Documents2.1 ASTM
7、Standards:2C 757 Specification for Nuclear-Grade Plutonium DioxidePowder, SinterableC 833 Specification for Sintered (Uranium-Plutonium) Di-oxide PelletsC 859 Terminology Relating to Nuclear Materials3C 1008 Specification for Sintered (Uranium-Plutonium) Di-oxide PelletsFast Reactor Fuel3. Terminolo
8、gy3.1 Definitions: For definitions of terms used in this stan-dard, refer to C 859.4. Summary of Dissolution Methods4.1 Most plutonium-containing samples are dissolved withvarious mineral acids and, except for plutonium metal, withapplied heat. Dissolution-resistant materials are dissolved inheated
9、and sealed containers in which pressurization providesa higher temperature than is attained at ambient pressure.4.2 Another dissolution technique is fusion of refractoryplutonium oxide with sodium bisulfate flux.4.3 The dissolved materials are quantitatively transferred toa tared polyethylene dispen
10、sing bottle for subsequent deliveriesof weight aliquants for high-precision analysis methods, suchas assays, or to a volumetric flask for deliveries of volumealiquants for less precise analysis methods, such as impurityanalyses. Acids, usually 1 M, are used as rinses to effectquantitative transfers
11、and as diluents in the polyethylenedispensing bottles and volumetric flasks. The use of water forthese purposes can, in some cases, result in hydrolysis ofplutonium to produce polymers that, although soluble, arenonreactive in separation treatments or in plutonium assaymethods that have no pretreatm
12、ents, such as fuming with acid.4.4 Plutonium metal is dissolved with hydrochloric acid orwith sulfuric acid.4.5 Plutonium oxide, calcined at about 1000C or lower, isdissolved with a mixture of hydrochloric, nitric, and hydrof-luoric acids using the sealed-reflux techniques (1).4Morerefractory pluton
13、ium oxide is dissolved with a fusion usingsodium bisuflate flux (2). Low-fired (650C) plutonium oxidecan also be dissolved in a mixture of nitric and hydrofluoricacids in beakers. Plutonium oxide fired at temperatures above1This practice is under the jurisdiction of ASTM Committee C26 on NuclearFuel
14、 Cycle and is the direct responsibility of Subcommittee C26.05 on Methods ofTest.Current edition approved Jan. 1, 2008. Published February 2008. Originallyapproved in 1990. Last previous edition approved in 2001 as C 1168 01.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcon
15、tact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.3Withdrawn.4The boldface numbers in parentheses refer to a list of references at the end ofthis practice.1Copyright ASTM International,
16、100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.Copyright by ASTM Intl (all rights reserved); Thu Feb 19 02:06:08 EST 2009Downloaded/printed byGuo Dehua (CNIS) pursuant to License Agreement. No further reproductions authorized.650C may also be dissolved in beakers
17、 using a mixture ofnitric and hydrofluoric acids when complete dissolution can bedemonstrated.4.6 Uranium-plutonium mixed oxide is dissolved in eitherof three ways: sodium bisulfate fusion, a heated mixture ofnitric and hydrofluoric acids in a beaker, or a mixture ofhydrochloric, nitric, and hydrofl
18、uoric acids by the sealed-refluxtechnique.4.7 Combinations of these dissolution techniques describedin 4.4 to 4.6 are sometimes used on difficult-to-dissolvesamples.4.8 Quantitative transfers of samples and subsequent solu-tion are required. Whenever a loss is incurred or even sus-pected, the sample
19、 is rejected. Solutions of dissolved samplesare inspected for undissolved particles; if particles are present,further treatment is necessary to attain complete solubility.When analyzing the dissolved sample for trace impurities,caution should be exercised so the dissolution process does notcause the
20、 impurity to be lost or does not significantly increasethe level of impurity being determined.5. Significance and Use5.1 The materials covered are plutonium metal, plutoniumoxide, and uranium-plutonium mixed oxide, including thosethat must meet ASTM product specifications.5.2 Plutonium and uranium m
21、ixtures are used as nuclearreactor fuels. For use as a nuclear reactor fuel, the materialmust meet certain criteria for combined uranium and pluto-nium content, effective fissile content, and impurity content asdescribed in Specifications C 757, C 833, and C 1008. Thematerial is assayed for plutoniu
22、m and uranium to determine ifthe content is correct as specified by the purchaser.5.3 The materials not covered are unique plutonium mate-rials, including alloys, compounds, and scrap materials. Theuser must determine the applicability of this practice to theseother materials. In general, these uniq
23、ue plutonium materialsare dissolved with various acid mixtures or by fusion withvarious fluxes. Many plutonium salts are soluble in hydrochlo-ric acid.6. Apparatus6.1 Balances, for weighing samples and solutions. A bal-ance with a sensitivity of 0.1 mg is necessary; however, abalance with 0.01 mg se
24、nsitivity is more desirable.Acalibratedbalance must be used.6.2 Beakers, Test Tubes, and Erlenmeyer FlasksGenerally, borosilicate glass is recommended; however, theanalyst should be sure that safety and sample contaminationfrom the container are considered when choosing appropriatecontainers.6.3 Fur
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