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ASTM C698-04
Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U, Pu)O2)
29 стр.
Заменен
Печатное изданиеЭлектронный (pdf)
138.84 $ (включая НДС 20%)
Разработчик:
Зарубежные/ASTM
ICS:
27.120.30 Fissile. Including raw materials / Делящиеся ядерные вещества. Включая сырье
Сборник (ASTM):
12.01 Nuclear Energy (I) / Ядерная энергия (I)
Тематика:
Nuclear Technology
Описание
Значение и использование

Mixed oxide, a mixture of uranium and plutonium oxides, is used as a nuclear-reactor fuel in the form of pellets. The plutonium content may be up to 10 weight %, and the diluent uranium may be of any 235U enrichment. In order to be suitable for use as a nuclear fuel, the material must meet certain criteria for combined uranium and plutonium content, effective fissile content, and impurity content as described in Specification C 833.

3.1.1 The material is assayed for uranium and plutonium to determine whether the plutonium content is as specified by the purchaser, and whether the material contains the minimum combined uranium and plutonium contents specified on a dry weight basis.

3.1.2 Determination of the isotopic content of the plutonium and uranium in the mixed oxide is made to establish whether the effective fissile content is in compliance with the purchaser’specifications.

3.1.3 Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not exceeded. Determination of impurities is also required for calculation of the equivalent boron content (EBC).

Область применения

1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade mixed oxides, (U, Pu)O2, powders and pellets to determine compliance with specifications.

1.2 The analytical procedures appear in the following order:

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. (For specific safeguard and safety precaution statements, see Sections 11, 20, 64, and 112 and 102.6.1.)

Ключевые слова:
Carbon content-nuclear materials