NSR Query Results

Output year order : Descending
Format : Normal

NSR database version of May 8, 2024.

Search: Author = J.Dawidowski

Found 6 matches.

Back to query form

2015GA07      Nucl.Instrum.Methods Phys.Res. A780, 27 (2015)

V.M.Galvan Josa, J.Dawidowski, J.R.Santisteban, F.Malamud, R.G.Oliveira

Model for neutron total cross-section at low energies for nuclear grade graphite

NUCLEAR REACTIONS C(n, X), E<10 eV; calculated σ. Comparison with available data.

doi: 10.1016/j.nima.2015.01.055
Citations: PlumX Metrics

2011VI02      Ann.Nucl.Energy 38, 1687 (2011)

A.D.Vinales, J.Dawidowski, J.I.Marquez Damian

Neutron total cross-section model for liquids and its application to light water

doi: 10.1016/j.anucene.2011.04.015
Citations: PlumX Metrics

2009RO32      Nucl.Instrum.Methods Phys.Res. B 267, 175 (2009)

L.A.Rodriguez-Palomino, F.Cantargi, J.J.Blostein, J.Dawidowski, J.R.Granada

Total cross section of solid mesitylene, toluene and a mixture of them at thermal neutron energies

NUCLEAR REACTIONS H(n, x), E=0.0013-94.4061 eV; measured products. Data were imported from EXFOR entry 31662.

doi: 10.1016/j.nimb.2008.11.040
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset31662.

2001BL10      Physica B304, 357 (2001)

J.J.Blostein, J.Dawidowski, J.R.Granada

On the Analysis of Deep Inelastic Neutron Scattering Experiments for Light Nuclei

doi: 10.1016/S0921-4526(01)00487-2
Citations: PlumX Metrics

2000DA17      Nucl.Instrum.Methods Phys.Res. B168, 462 (2000)

J.Dawidowski, J.R.Granada, J.J.Blostein

Neutron Total Cross-Sections of Normal and Deuterated Ethanol in the Thermal and Epithermal Energy Ranges

NUCLEAR REACTIONS ^1,2H, C, O(n, X), E=low; measured total σ for normal, deuterated ethanol.

doi: 10.1016/S0168-583X(00)00006-9
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset31504.

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.