Comparison of Measured and Evaluated Spectrum-Averaged Cross-Section Data for Reactor Neutron Metrology

Zijp, W.L.; Rieffe, H.C.; Nolthenius, H. J.

doi:10.1007/978-94-009-7099-1_83

Cited by 3 publications

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“…However, a survey in the literature [7 -11] indicates that the relevant experimental data are old (more than a decade) and a marked discrepancy still exists between calculated and measured values of CT for several threshold reactions (see for example references [7] and [11]). Furthermore, the uncertainties in the contemporary knowledge of these cross sections are in general somewhat larger than is desirable for dosimetry applications.…”

Section: Introductionmentioning

confidence: 99%

Average Neutron Gross Section Measurements in U-235 Fission Spectrum for Some Threshold Reactions

1992

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Integral cross section / Activation technique / Fission spectrum / Threshold reactions / Fast neutron dosimetry / Neutron spectrum unfolding AbstractFission neutron spectrum averaged cross sections have been measured for the threshold reactions "Ni(n, 2n)"Ni, 2n)'"I, "Mn(n, 2n)='^Mn, "Cu(n, a)®»Co and "P(n, p)3'Si, by the activation technique using high-resolution y-ray spectroscopy. The fast neutron spectrum at the Irradiation position has been characterized by using an additional set of activation foils. The results are presented with a complete uncertainty covariance matrix and are compared with evaluated values and previous measurements.

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Section: Introductionmentioning

confidence: 99%

Average Neutron Gross Section Measurements in U-235 Fission Spectrum for Some Threshold Reactions

1992

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“…Legacy dosimetry files, e.g., DOSDAM77 [1] and IRDF-90 [2], addressed isotopic-specific reactions of interest for dosimetry monitoring applications. However, most applications use elemental, and not isotopically enriched, activation sensors.…”

Section: Activation Sensorsmentioning

confidence: 99%

Importance of cross reaction covariance data for user applications

Griffin¹

2023

EPJ Web Conf.

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The characterization of the uncertainty in radiation damage metrics presents many challenges. This paper examines the current approaches to characterizing radiation damage metrics such as hydrogen and helium gas production, material heating, trapped charge in microelectronics, and lattice displacement damage. Critical uncertainty aspects go beyond just the material cross sections and involve the consideration of energy-dependent cross reaction correlations, the recoil ion energy spectrum, and models used for the partitioning of the recoil ion energy into various forms of energy deposition. This paper starts with a review of terminology and then examines the current approaches in the characterization of uncertainty in radiation damage metrics for several applications. The major deficiencies in the uncertainty of the damage metric characterization are also identified.

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“…In the first part of the experiment [1] attention was paid to install an adequate irradiation device near the reactor core, to characterize the neutron spectrum at the irradiation position and to measure averaged neutron cross sections for a particular set of threshold reactions. In the present paper, another important set of threshold reactions, listed in Table 1, was investigated as an effort to establish the origin of some discrepancies between calculated and measured values of σ (see for example references [2,3] and [4]) and to provide new experimental information on these parameters with lower overall uncertainties than those reported in the literature. The reactions 55 Mn(n,2n) and 58 Ni(n,2n) have again been included in this study because of the very discrepant σ result reported recently by Horibe [5] for the former reaction and because of the large difference (50%) [3] which still exists between calculated and measured values of σ for the latter reaction.…”

Section: Introductionmentioning

confidence: 98%

Measurements of U-235 Fission Neutron Spectrum Averaged Cross Sections for Threshold Reactions

1994

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Integral cross section / Activation technique / Fission spectrum / Threshold reactions / Fast neutrons dosimetry / Neutron spectrum unfolding AbstractMeasurements of fission neutron spectrum averaged cross sections have been performed for several activation reactions, with thresholds in the energy interval from 1.2 to 13.5 MeV, by using high resolution y-ray spectroscopy. The results obtained are presented with a complete uncertainty covariance matrix and are compared with evaluated values and previous measurements.

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Comparison of Measured and Evaluated Spectrum-Averaged Cross-Section Data for Reactor Neutron Metrology

Cited by 3 publications

References 0 publications

Average Neutron Gross Section Measurements in U-235 Fission Spectrum for Some Threshold Reactions

Average Neutron Gross Section Measurements in U-235 Fission Spectrum for Some Threshold Reactions

Importance of cross reaction covariance data for user applications

Measurements of U-235 Fission Neutron Spectrum Averaged Cross Sections for Threshold Reactions

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