ASTM-E692 2008(Redline)

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E692-08 Standard Test Method for Determining the Content of Cesium-137 in Irradiated Nuclear Fuels by High-Resolution Gamma-Ray Spectral Analysis (Redline)

Published By	Publication Date	Number of Pages
ASTM	2008	4

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Categories: 27.120.30 - Fissile materials and nuclear fuel technology, ASTM

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Description

Significance and Use

This test method uses a high-resolution gamma-ray spectrometer as a basis for measuring the gamma-ray emission rate of ¹³⁷ Cs- ^137m Ba 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 (HNO ₃ ) 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 10 ⁵ 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.

1. Scope

1.1 This test method covers the determination of the number of atoms of ¹³⁷ Cs 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.

1.2 ¹³⁷ Cs is not suitable as a fission monitor for samples that may have lost cesium during reactor operation. For example, a large temperature gradient enhances ¹³⁷ Cs 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 ¹³⁷ Cs distribution should alert the analyst to the potential loss of the fission product nuclide. The ¹³⁷ Cs 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 ¹³⁷ Cs distribution with the distribution of nonmigrating fission-product nuclides such as ⁹⁵ Zr or ¹⁴⁴ Ce would indicate the relative degree of ¹³⁷ Cs 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.

2. Referenced Documents (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.

ASTM Standards

E170 Terminology Relating to Radiation Measurements and Dosimetry E181 Test Methods for Detector Calibration and Analysis of Radionuclides E219 Test Method for Atom Percent Fission in Uranium Fuel (Radiochemical Method) (Discontinued 2001) E267 Test Method for Uranium and Plutonium Concentrations and Isotopic Abundances E321 Test Method for Atom Percent Fission in Uranium and Plutonium Fuel (Neodymium-148 Method)

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 Code

ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)

DOI: 10.1520/E0692-08 ASTM International is a member of CrossRef.

ASTM E692 (Nuclear Technology Standards)

Citing ASTM Standards

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Additional information

Standard Title	E692-08 Standard Test Method for Determining the Content of Cesium-137 in Irradiated Nuclear Fuels by High-Resolution Gamma-Ray Spectral Analysis (Redline)
Published Code	ASTM
Publication Date	2008
Pages Count	4
ICS Codes	27.120.30 - Fissile materials and nuclear fuel technology

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ASTM-E692 2008(Redline)

ASTM E692 (Nuclear Technology Standards)

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