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NSR database version of April 27, 2024.

Search: Author = R.Wittman

Found 4 matches.

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2021MO02      Nucl.Instrum.Methods Phys.Res. A990, 164987 (2021)

M.E.Moore, A.V.Mozhayev, R.S.Wittman, E.K.Mace

Configuration and impurity quantification of AmLi sources using radiography and gamma spectroscopy

NUCLEAR REACTIONS ⁷Li(α, α'), ⁹Be(α, n), ²³Na(α, p), E<10 MeV; calculated alpha particle range and fluence parameters.

doi: 10.1016/j.nima.2020.164987
Citations: PlumX Metrics

2020PI02      Nucl.Data Sheets 163, 249 (2020)

B.D.Pierson, L.R.Greenwood, S.C.Stave, J.T.Burke, S.W.Padgett, A.M.Prinke, J.M.Goda, J.A.Bounds, D.K.Hayes, A.S.Tamashiro, R.S.Wittman, G.Slavik, M.P.Dion, J.G.Burch, T.S.Palmer

Improved Cumulative Fission Yield Measurements with Fission Spectrum Neutrons on ²³⁸U

NUCLEAR REACTIONS ²³⁸U(n, F)⁸⁴Br/⁹³Y/⁹⁴Y/¹⁰⁴Tc/¹²⁸Sn/¹²⁹Sb/¹³⁰Sb/¹³¹Te/¹³³I/¹³⁴I/¹³⁵I/¹³⁸Xe/¹³⁹Ba/¹⁴¹Ba/¹⁴²Ba/¹⁴²La/¹⁴⁶Ce/¹⁴⁹Nd, E ∼ 2 MeV; measured fission products, Eγ, Iγ; deduced fission yields. Comparison with ENDF/B-VIII.0 library evaluations.

doi: 10.1016/j.nds.2019.12.006
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14584.

2019PI01      Nucl.Data Sheets 155, 86 (2019)

B.D.Pierson, A.M.Prinke, L.R.Greenwood, S.C.Stave, R.S.Wittman, J.G.Burch, J.T.Burke, S.W.Padgett, J.J.Ressler, G.Slavik, A.Tamashiro, A.Tonchev, W.Younes

Improved Cumulative Fission Yield Measurements with Fission Spectrum Neutrons on ²³⁵U

NUCLEAR REACTIONS ²³⁵U(n, F)⁸⁴Br/⁸⁹Rb/⁹¹Sr/⁹³Y/⁹⁷Zr/¹⁰¹Mo/¹⁰⁵Ru/¹²⁸Sn/¹²⁹Sb/¹³⁰Sb/¹³¹Sb/¹³¹Te/¹³³I/¹³⁵I/¹⁴¹Ba/¹⁴²Ba/¹⁴²La/⁸⁹Rb/⁹³Y/¹²⁸Sn/¹²⁹Sb/¹³⁰Sb/⁹⁴Y/¹³⁴Te/¹³⁴I/¹³⁸Xe, E ∼ 2 MeV; measured fission products, Eγ, Iγ; deduced cumulative fission yields.

doi: 10.1016/j.nds.2019.01.005
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14512.

2015FI11      J.Radioanal.Nucl.Chem. 306, 79 (2015)

E.C.Finn, L.Metz, L.Greenwood, B.Pierson, R.Wittman, J.Friese, R.Kephart

Cumulative fission yields of short-lived isotopes under natural-abundance-boron-carbide-moderated neutron spectrum

NUCLEAR REACTIONS ^233,235,238U, ²³⁹Pu, ²³⁷Np(n, F)⁸⁴Br/⁸⁷Kr/⁸⁹Rb/⁹⁰Rb/⁹¹Sr/⁹²Sr/⁹³Sr/⁹³Y/⁹⁴Y/⁹⁴Sr/⁹⁵Y/⁹⁵Zr/⁹⁷Zr/¹⁰⁰Mo/¹⁰¹Mo/¹⁰³Ru/¹⁰⁴Tc/¹⁰⁵Ru/¹²⁹Sb/¹³⁰Sn/¹³¹I/¹³¹Sb/¹³⁹Ba/¹⁴⁰Ba/¹⁴¹Ba/¹⁴¹Ce/¹⁴²La/¹⁴³Ce/¹⁴⁵Ce/¹⁴⁶Ce/¹⁴⁷Nd/¹⁴⁹Nd, E ∼ 700 keV; measured fission products; deduced fission yields. Comparison with ENDF/B-VII.1, JEFF-3.1.1 and JENDL-4 libraries.

doi: 10.1007/s10967-015-4085-6
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14441.

Note: The following list of authors and aliases matches the search parameter R.Wittman: , R.S.WITTMAN