NSR Query Results


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NSR database version of May 3, 2024.

Search: Author = D.F.da Cruz

Found 4 matches.

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2014DA05      Nucl.Technology 185, 174 (2014)

D.F.Da Cruz, D.Rochman, A.J.Koning

Uncertainty Analysis on Reactivity and Discharged Inventory Due to 235, 238U, 239, 240, 241Pu, and Fission Products: Application to a Pressurized Water Reactor Fuel Assembly

NUCLEAR REACTIONS 235,238U, 239,240,241Pu(n, F), E thermal; analyzed uncertainties for keff, fission yield and products. Comparison with available data.

doi: 10.13182/NT12-154
Citations: PlumX Metrics


2014DA12      Nucl.Data Sheets 118, 531 (2014)

D.F.da Cruz, D.Rochman, A.J.Koning

Quantification of Uncertainties due to 235, 238U, 239, 240, 241Pu and Fission Products Nuclear Data Uncertainties for a PWR Fuel Assembly

doi: 10.1016/j.nds.2014.04.126
Citations: PlumX Metrics


2012RO20      Nucl.Technology 179, 323 (2012)

D.Rochman, A.J.Koning, D.F.Da Cruz

Propagation of 235, 236, 238U and 239Pu Nuclear Data Uncertainties for a Typical PWR Fuel Element

doi: 10.13182/NT11-61
Citations: PlumX Metrics


2010RO01      Nucl.Instrum.Methods Phys.Res. A612, 374 (2010)

D.Rochman, A.J.Koning, D.F.da Cruz, P.Archier, J.Tommasi

On the evaluation of 23Na neutron-induced reactions and validations

COMPILATION 23Na; compiled evaluated nuclear reaction data.

doi: 10.1016/j.nima.2009.10.147
Citations: PlumX Metrics


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