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NSR database version of May 8, 2024.

Search: Author = R.E.Mayer

Found 6 matches.

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2009TA11      Appl.Radiat.Isot. 67, 1711 (2009)

A.Tartaglione, J.J.Blostein, R.E.Mayer

Prompt gamma emissions in the reaction ¹¹⁵In(n, γ)¹¹⁶In for neutrons around the 1.45 eV absorption resonance

NUCLEAR REACTIONS ¹¹⁵In(n, γ), E=1.45 eV; measured Eγ, Iγ, yields for prompt emissions.

doi: 10.1016/j.apradiso.2009.03.078
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset31677.

1995CU04      Nucl.Instrum.Methods Phys.Res. A 357, 519 (1995)

G.J.Cuello, J.R.Santisteban, R.E.Mayer, J.R.Granada

Total neutron cross section of Teflon between 0.00038 and 590 eV

NUCLEAR REACTIONS C(n, x), ¹⁹F(n, x), E=3.758E-4-600.0 eV; measured products, ¹⁹F; deduced σ, σ(E). Data were imported from EXFOR entry 31426.

doi: 10.1016/0168-9002(94)01535-X
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset31426.

1990GR05      J.Nucl.Sci.Technol.(Tokyo) 27, 222 (1990)

J.R.Granada, R.E.Mayer, G.Guido, P.C.Florido, A.Larreteguy, V.H.Gillette, N.E.Patino, J.Converti, S.E.Gomez

Thermal Neutron Measurements on Electrolytic Cells with Deuterated Palladium Cathodes Subjected to a Pulsed Current

NUCLEAR REACTIONS ²H(d, n), E=low; measured neutron production. Electrolytic cells, LiH dissolved in D₂O, Pd cathodes.

doi: 10.1080/18811248.1990.9731174
Citations: PlumX Metrics

1987GR31      Phys.Rev. A36, 5594 (1987)

J.R.Granada, V.H.Gillette, R.E.Mayer

Calculation of Neutron Cross Sections and Thermalization Parameters for Molecular Gases using a Synthetic Scattering Function. II. Application to H₂O, D₂O, and C₆H₆

NUCLEAR REACTIONS ¹H, O, C(n, n), E=thermal; calculated σ, thermalization parameters. Synthetic model, H₂O, D₂O, C₆H₆ moderators.

doi: 10.1103/PhysRevA.36.5594
Citations: PlumX Metrics

1987GR38      Nucl.Instrum.Methods Phys.Res. A 261, 573 (1987)

J.R.Granada, J.Dawidowski, R.E.Mayer, V.H.Gillette

Thermal neutron cross section and transport properties of polyethylene

NUCLEAR REACTIONS H(n, x), E=0.001035-8.75 eV; measured products; deduced σ, σ(E). Data were imported from EXFOR entry 30748.

doi: 10.1016/0168-9002(87)90370-6
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset30748.

1978KR08      Atomkernenergie 31, 42 (1978)

F.Kropff, J.R.Granada, R.E.Mayer, L.A.Remez

Total Neutron Cross Section of Molybdenum in the Thermal Range

NUCLEAR REACTIONS Mo(n, X), E=0.0016-10 eV; measured total σ(E).

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset30413.