1.1 This test method covers the precise determination of lead and cadmium extracted by acetic acid from glazed ceramic surfaces under boiling conditions. The procedure of extraction may be expected to accelerate the release of lead and cadmium from the glaze and to serve, therefore, as a severe test that simulates the most severe conditions of usage of such ceramic cookware. This method is specific for lead and cadmium. 1.2 This test method is applicable to ceramic cookware intended for use in contact with food, for example cookware made of china, crockery, porcelain, and earthenware. 1.3 This standard does not purport to address the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

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1.1 This specification covers copper-beryllium alloy rod and bar in straight lengths. The following three alloys are covered: Copper alloy Nominal Beryllium UNS No. 2 Content, % C17000 1.7 C17200 1.9 C17300 1.9 +0.4 lead 1.2 Unless otherwise required, Copper Alloy UNS C17200 shall be the alloy furnished whenever Specification B 196M is specified without any alloy designation. Note 1-This specification is the metric companion of Specification B 196.

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1.1 This specification provides limits for the extraction of lead and cadmium from glazed ceramic surfaces under boiling conditions. It is applicable to ceramic cookware intended for use in contact with food, for example cookware made of china, crockery, porcelain, and earthenware.

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1.1 This specification covers the requirements for impervious steatite ceramics having low electrical loss characteristics for use in electronic and electrical applications. 1.2 Impervious steatite ceramics described in this specification shall be designated as Type I, Type II, Type III, and Type IV. 1.3 The values stated in inch-pound units are to be regarded as the standard.

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1.1 This specification establishes the requirements for naval brass rod, bar, and shapes produced from Copper Alloys UNS Nos. C46200, C46400, C47940, C48200, or C48500. 1.1.1 For piston-finish rod or shafting, refer to Section 9. 1.2 This specification is the companion to inch-pound Specification B21. 1.3 Warning-Mercury is a definite health hazard in use and disposal (see 8.1). Note 1-For hot forging material, refer to Specification B124.

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1.1 This test method covers the determination of U atom percent fission that has occurred in U fuel from analysis of the 137 Cs to U ratio after irradiation. 1.2 The test method is applicable to high-density, clad U fuel (metal, alloy, ceramic compound) in which no separation of Cs and U has occurred. 1.3 The test method is best applied to fuels that have aged several months since irradiation. In such material, the 13-day 136 Cs activity is reduced to a small amount through decay (3). 1.4 The test method should be restricted to low-exposure samples in which the activity of 134 Cs is less than that of 137 Cs. Cesium-134 is produced by neutron capture on fission product 133 Cs and grows at a rate proportional to the square of the exposure. This capture process limits the test method to samples exposed to less than 0.6 X 10 nvt. This exposure corresponds to burnups of 12 gigawatt days per metric ton of uranium (GWD/MTU) in Yankee Core I, and 5 GWD/ MTU in Dresden Core I. Samples with higher exposures may require the use of a lithium-drifted germanium detector to obtain adequate resolution between 134 Cs and 137 Cs. The use of such a detector will extend the range of this test method by a factor of about 2. Mass spectrometric isotope dilution analysis of 137 Cs with 133 Cs as the isotopic diluent would also overcome 134 Cs interference. 1.5 The test method is best applied to fuels where overheating has not caused center melting or grain growth, since high temperatures cause 137 Cs to distill from the fuel and deposit on cooler regions, such as the cladding. Therefore, cladding should be leached in the dissolver solution or dissolved with the uranium to maintain the true ratio of fission product 137 Cs to U. Alternatively, burnup in a maximum flux region of a fuel element can be obtained from analyzing a low-flux region of the element. The burnup measured in this position can be related to the burnup in the peak-flux position by a gamma scan of the element. A gamma scan usually represents the distribution of zirconium-95 and is a reflection of the fission distribution integrated over only the most recent months. This is not always a serious disadvantage, since such studies may be made after short irradiations. 1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

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1.1 These test methods cover procedures for determining the gross camber of ceramic substrates in a free (nonclamped) state and for appraising the quality of a substrate lot by relating the deviation from flatness of faces due to curvature. 1.2 These test methods are applicable to substrates of sizes ranging up to 4 in. (102 mm) in the maximum dimension. 1.3 In principle, these test methods may be applied to larger dimensioned substrates. 1.4 The values stated in inch-pound units are to be regarded as the standard. 1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

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1.1 This practice covers alkaline fusion of silicate matrix samples (or other matrices difficult to dissolve in acids) using an electric Bunsen burner mounted on an orbital shaker. This practice has been used successfully to dissolve borosilicate glass, dried glass melter feeds, various simulated nuclear waste forms, and dried soil samples. 1.2 This fusion apparatus and the alkaline fluxes described are suitable for use in shielded radiation containment facilities such as hot cells and shielded hoods. 1.3 When samples dissolved using this practice are radioactive, the user must follow radiation protection guidelines in place for such materials. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. Specific precautionary statements are given in Section 8.

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1.1 These test methods cover the rapid and inexpensive analysis of coal and coke ash for the commonly determined major elements. 1.2 The test methods appear in the following order: Sections Silicon Dioxide (SiO2) 10 to 12 Aluminum Oxide (Al2O3) 13 to 15 Ferric Oxide (Fe2O3) 16 to 18 Titanium Dioxide (TiO2) 19 to 22 Phosphorus Pentoxide (P2O5) 23 to 25 Calcium Oxide (CaO), and Magnesium Oxide (MgO) 26 to 29 Sodium Oxide (Na2O) and Potassium Oxide (K2O) 30 to 33 1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only. 1.4 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

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