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Scope

1.1 This test method covers the determination of the number of atoms of ¹³⁷Cs in aqueous solutions of irradiated uranium and plutonium nuclear fuel. When combined with a method for determining the initial number of fissile atoms in the fuel, the results of this analysis allows atom percent fission (burn-up) to be calculated (1). The determination of atom percent fission, uranium and plutonium concentrations, and isotopic abundances are covered in Test Methods E 267 and E 321.

1.2 ¹³⁷Cs is not suitable as a fission monitor for samples that may have lost cesium during reactor operation. For example, a large temperature gradient enhances ¹³⁷Cs migration from the fuel region to cooler regions such as the radial fuel-clad gap, or, to a lesser extent, towards the axial fuel end.

1.3 A nonuniform ¹³⁷Cs distribution should alert the analyst to the potential loss of the fission product nuclide. The ¹³⁷Cs distribution may be ascertained by an axial gamma-ray scan of the fuel element to be assayed. In a mixed-oxide fuel, comparison of the ¹³⁷Cs distribution with the distribution of nonmigrating fission-product nuclides such as ⁹⁵Zr or ¹⁴⁴Ce would indicate the relative degree of ¹³⁷Cs migration.

1.4 The values stated in SI units are to be regarded as standard. No other unites of measurement are included in this 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.

Significance and Use

This test method uses a high-resolution gamma-ray spectrometer as a basis for measuring the gamma-ray emission rate of ¹³⁷Cs-^137mBa in a dilute nitric acid solution containing 10 mg/L of cesium carrier. No chemical separation of the cesium from the dissolved-fuel solution is required. The principal steps consist of diluting a weighed aliquot of the dissolved-fuel solution with a known mass of 1 M nitric acid (HNO₃) and measuring the 662 keV gamma-ray count rate from the sample, then measuring the 662 keV gamma-ray count rate from a standard source that has the same physical form and counting geometry as the sample.

The amount of fuel sample required for the analysis is small. For a sample containing 0.1 g of fuel irradiated to one atom percent fission, a net count rate of approximately 10⁵ counts per second will be observed for a counting geometry that yields a full-energy peak efficiency fraction of 1 × 10^-3. The advantage of this small amount of sample is that the concentration of fuel material can be kept at levels well below 1 g/L, which results in negligible self-absorption in the sample aliquot and a small radiation hazard to the analyst.

Keywords

Cesium-137; gamma-ray spectrometer; nuclear fuel; percent fission; Cesium-137; Gamma radiation--nuclear materials/applications; High-resolution gamma-ray spectral analysis; Nuclear fuels (reactor); Plutonium; Uranium; ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)

To find similar documents by ASTM Volume:

12.01 (Nuclear Energy (I))

To find similar documents by classification:

27.120.30 (Fissile materials and nuclear fuel technology Including raw materials Radioactive wastes, see 13.030.30)

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