Assay of fissile materials by a cyclic method of neutron activation and delayed-neutron counting

MacMurdo, K.W.; Bowman, W.W.

doi:10.1016/0029-554x(77)90779-0

Cited by 17 publications

(9 citation statements)

References 7 publications

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“…If all the times during an assay are the same from shuffle to shuffle, the number of delayed-neutron counts is given by Eq. (17). In practice, the times can show variations, although their differences (a few milliseconds) are not significant.…”

Section: A Delayed-neutron Counts With Irregular Timesmentioning

confidence: 98%

“…• (n,p) reactions in 17 O that can lead to delayed neutrons from the decay of 17 N with a half-life of 4.17 s 11 " 13 (Although this has been observed in reactor cooling water, the cross section and delayed-neutron yield are too small to be detected with the lower irradiating neutron fluxes in a shuffler. ); and…”

Section: Interfering Sources Of Neutronsmentioning

confidence: 99%

“…The ratio of Eqs. (17) and (28) compares the uniform case to the irregular case and is independent of detection efficiency and fission rate; this is called the cycle correction Different assays may use different numbers of shuffles. A correction must be made before these counts can be compared, as with a single calibration curve.…”

Section: B Adjusting Counts For Irregular Timesmentioning

confidence: 99%

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Shuffler instruments for the nondestructive assay of fissile materials

Rinard¹

1991

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atomic weight of fission target material assay result [g, g/L] bias corrected assay value estimate of assay result atomic weight of isotope i in the fission target material interpolated assay result coefficient for isotope i for assay of a mixture of isotopes estimated background counts during an assay = Bf,(TJt b) background counts during a count time fy background count rate from delayed-neutron detector [s" 1 ] parameters in the bias correction function background count rate from flux monitor [s~l] total counts (signal plus background) counts in the delayed-neutron detectors during an assay counts in the flux monitor detectors during an assay counts from the delayed-neutron detectors during shuffle k counts in the flux monitor detectors during shuffle k 252 Cf decay correction factor xi SHUFFLER INSTRUMENTS FOR THE NONDESTRUCTIVE ASSAY OF FISSILE MATERIALS

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Section: A Delayed-neutron Counts With Irregular Timesmentioning

confidence: 98%

Section: Interfering Sources Of Neutronsmentioning

confidence: 99%

Section: B Adjusting Counts For Irregular Timesmentioning

confidence: 99%

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Shuffler instruments for the nondestructive assay of fissile materials

Rinard¹

1991

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“…As many as 50 individual delayed neutron emitters, each with a characteristic half-life in the range of about 0.2-56 s, probably exist among the total gross fission products (MacMurdo and Bowman, 1977). It generally is agreed, however, that an optimum least-squares fit to experimental neutron decay data, regardless of parent isotope, is obtained using only six half-life groups.…”

Section: Delayed Neutronsmentioning

confidence: 99%

Methods for geochemical analysis

Baedecker¹

1987

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“…The problem of cyclic irradiation with an isotropic neutron source and counting delayed neutrons has been previously analyzed to determine the combination of pulse time, count time, and optimum number of cycles to produce the maximum detector counts for a given irradiation time (Alfassi 1990;Spyrou 1982;MacMurdo 1977). In the Alfassi analysis, it was determined that one would want the count time and pulse time equal, which was the same conclusion that this project reached as described in section 4.4.…”

Section: 7mentioning

confidence: 99%