NSR Query Results


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NSR database version of May 8, 2024.

Search: Author = V.H.Gillette

Found 4 matches.

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1999GI05      Ann.Nucl.Energy 26, 1167 (1999)

V.H.Gillette, M.M.Sbaffoni, J.R.Granada, M.E.Pepe

Thermal Neutron Cross Sections for Moderator Materials: Comparison of a synthetic scattering function and NJOY results

NUCLEAR REACTIONS H(n, X), E=thermal; calculated total σ for various moderator materials. Synthetic scattering function. Comparison with data.

doi: 10.1016/S0306-4549(98)00097-8
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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
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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
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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
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset30748.


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