Levels and gamma energies of<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" display="inline"><mml:mrow><mml:mmultiscripts><mml:mrow><mml:mi mathvariant="normal">Al</mml:mi></mml:mrow><mml:mprescripts /><mml:mrow /><mml:mrow><mml:mn>28</mml:mn></mml:mrow><mml:mrow /><mml:mrow /></mml:mmultiscripts></mml:mrow></mml:math>studied by thermal neutron capture

Schmidt, Hartwig; Hungerford, P.; Daniel, H.; Egidy, T. von; Kerr, S. A.; Brissot, R.; Barreau, G.; Börner, H. G.; Hofmeyr, C.; Lieb, Klaus

doi:10.1103/physrevc.25.2888

Cited by 24 publications

(11 citation statements)

References 19 publications

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“…Using data of absolute intensities of decay and prompt γ-rays are taken from [2][3][4][5][6][7][8][9][10][11][12][13][14]. The efficiency was determined from thermal neutron capture γ-rays.…”

Section: Resultsmentioning

confidence: 99%

Reliability of Prompt γ-Ray Intensities for the Measurement of Neutron Capture Cross Sections

Miyazaki

Shimizu²,

Shibata³

et al. 2005

AIP Conference Proceedings

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Articles you may be interested inDetermination of radiative neutron capture cross sections for unstable nuclei by the γ-ray strength function method AIP Conf.Abstract. We examined the reliability of prompt γ-ray intensities by measuring ratios of thermal neutron capture cross sections on 23 Na, 27 Al, 51 V, 55 Mn, 64 Ni, 65 Cu, 141 Pr, 186 W, and 197 Au at the Kyoto University Research Reactor Institute. The cross sections were obtained by two methods: the first is detecting prompt γ-rays (which we call the prompt-γ method), and the other is detecting γ-rays following β-decay (the activation method). Intensities of prompt γ-rays and decay γ-rays have been reported to have an uncertainty of about 5% and 1%, respectively. It is found that values of 65 Cu and 186 W have large discrepancies in the results of the two methods, by about 30%. The disagreement would be caused by inaccuracy of the absolute intensities of prompt γ-rays. The inaccuracy is estimated to be due to the incompleteness of level schemes and the detector efficiency of prompt γ-rays. We need to examine absolute intensities of prompt γ-rays when we use the prompt-γ method.

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Section: Resultsmentioning

confidence: 99%

Reliability of Prompt γ-Ray Intensities for the Measurement of Neutron Capture Cross Sections

Miyazaki

Shimizu²,

Shibata³

et al. 2005

AIP Conference Proceedings

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“…The intensity is the number of photons of a particular energy produced for every 100 neutron capture reactions. Many of the gamma-rays not reported by Schmidt (1982), but included in Lone (1981), were concluded to be doubtful AI capture lines by Schmidt.…”

Section: Appendix Amentioning

confidence: 98%

Photon production assessment for the MCNP{trademark} data libraries

Frankle¹

1996

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The goal of the Multispectral Neutron Logging project was to estimate minimum detection thresholds for environmental contaminants using nuclear well-logging techniques. The specific method was to identify and quantify contaminants from the discrete photons from thermal neutron capture reactions in the formation. Computer simulations using MCNP4A were used to benchmark the computer code against experimental data, and then to predict minimum detection thresholds for other contaminants. High quality photon-production data for MCNP was required for this project. The goal of this work was to assess photon production at thermal neutron energies. This work was extended to include higher energy neutron reactions, En=1-14 MeV. Additionally, the assessment was expanded to include all nuclides and not only the contaminants of interest. This report documents the results of the assessment, and makes general recommendations for the user. Ultimately, it is the responsibility of all users to ensure that the data they are using is appropriate for their particular application. This assessment process reinforced the need for higher quality photon-production spectra for use in the Multispectral Neutron Logging project, as well as for other applications.MCNP is a trademark of the Regents

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“…The reaction of interest for aluminum is 27 Al(n,γ) 28 Al with a β − transition to 28 Si [62]. The transition releases 4.642 MeV and results in an excited state of 28 Si at 1.779 MeV; therefore the β − endpoint energy is 2.864 MeV.…”

Section: Aluminummentioning

confidence: 99%

Nonfuel antineutrino contributions in the ORNL High Flux Isotope Reactor (HFIR)

Balantekin¹,

Band²,

Bass³

et al. 2020

Phys. Rev. C

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Reactor neutrino experiments have seen major improvements in precision in recent years. With the experimental uncertainties becoming lower than those from theory, carefully considering all sources of νe is important when making theoretical predictions. One source of νe that is often neglected arises from the irradiation of the nonfuel materials in reactors. The νe rates and energies from these sources vary widely based on the reactor type, configuration, and sampling stage during the reactor cycle and have to be carefully considered for each experiment independently. In this article, we present a formalism for selecting the possible νe sources arising from the neutron captures on reactor and target materials. We apply this formalism to the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory, the νe source for the the Precision Reactor Oscillation and Spectrum Measurement (PROSPECT) experiment. Overall, we observe that the nonfuel νe contributions from HFIR to PROSPECT amount to 1% above the inverse beta decay threshold with a maximum contribution of 9% in the 1.8-2.0 MeV range. Nonfuel contributions can be particularly high for research reactors like HFIR because of the choice of structural and reflector material in addition to the intentional irradiation of target material for isotope production. We show that typical commercial pressurized water reactors fueled with low-enriched uranium will have significantly smaller nonfuel νe contribution.

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Levels and gamma energies ofAl28studied by thermal neutron capture

Cited by 24 publications

References 19 publications

Reliability of Prompt γ-Ray Intensities for the Measurement of Neutron Capture Cross Sections

Reliability of Prompt γ-Ray Intensities for the Measurement of Neutron Capture Cross Sections

Photon production assessment for the MCNP{trademark} data libraries

Nonfuel antineutrino contributions in the ORNL High Flux Isotope Reactor (HFIR)

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