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NSR database version of May 10, 2024.

Search: Author = E.J.Axton

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1986AX01      Ann.Nucl.Energy 13, 627 (1986)

E.J.Axton

The Thermal-Neutron Absorption Cross-Sections of Mn and S

NUCLEAR REACTIONS S, Mn(n, γ), E=thermal; calculated absorption σ. Mn-bath dilution techniques.

doi: 10.1016/0306-4549(86)90021-6
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 datasetV0042.

1985AX01      Ann.Nucl.Energy 12, 315 (1985)

E.J.Axton

The Thermal-Neutron Capture Cross-Section of ⁵⁵Mn

NUCLEAR REACTIONS ⁵⁵Mn(n, γ), E=thermal; analyzed data; deduced capture σ. Other evaluations input.

doi: 10.1016/0306-4549(85)90035-0
Citations: PlumX Metrics

1985AX02      Metrologia 21, 59 (1985)

E.J.Axton, A.G.Bardell

Neutron yield from the spontaneous fission of ²⁵²Cf (ν-bar)

RADIOACTIVITY ²⁵²Cf(SF); measured decay products, En, In; deduced yields, neutron multiplicity, their uncertainties and correlation matrix.

doi: 10.1088/0026-1394/21/2/003
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset22004.

1969RO38      J.Nucl.Energy 23, 205 (1969)

J.C.Robertson, T.B.Ryves, E.J.Axton, I.Goodier, A.Williams

A Measurement of the Radiative Capture Cross Section of Gold at an Energy of 966 keV

NUCLEAR REACTIONS ¹⁹⁷Au(n, γ), E=966 keV; measured σ.

doi: 10.1016/0022-3107(69)90002-1
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset21199.

1968WH04      J.Nucl.Energy 22, 73 (1968)

P.H.White, E.J.Axton

Measurement of the Number of Neutrons Per Fission for ²⁵²Cf

RADIOACTIVITY, Fission ²⁵²Cf; measured fission rate, neutron number; deduced average number of prompt neutrons/spontaneous fission.

doi: 10.1016/0022-3107(68)90056-7
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset21198.