P.G. Young
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View article: The status of nuclear data evaluations for Version VI of ENDF/B
The status of nuclear data evaluations for Version VI of ENDF/B Open
A new version of the United States national evaluated nuclear data file, ENDF/B-VI, is nearing completion. Major emphasis is being placed on correcting some long-standing nuclear data problems that adversely affect applied calculations for…
View article: Calculation of /sup 235/U(n,n') cross sections for ENDF/B-VI
Calculation of /sup 235/U(n,n') cross sections for ENDF/B-VI Open
Cross sections for neutron-induced reactions on /sup 235/U between 0.01 and 20 MeV have been calculated in a preliminary analysis for the ENDF/B-VI evaluation with particular emphasis on neutron inelastic scattering. A deformed optical mod…
View article: Global and local optical model parameterizations. [A > 40, 10 keV-20 MeV]
Global and local optical model parameterizations. [A > 40, 10 keV-20 MeV] Open
A review is given of global and regional phenomenological neutron optical model parameterizations in the mass region above A = 40 and for neutron energies in the range 10 keV to 20 MeV. The performance of some 11 different neutron paramete…
View article: Calculation of neutron cross sections on iron up to 40 MeV
Calculation of neutron cross sections on iron up to 40 MeV Open
The development of high energy d + Li neutron sources for fusion materials radiation damage studies will require neutron cross sections up to 40 MeV. Experimental data above 15 MeV are generally sparse or nonexistent, and reliance must be …
View article: Calculation of /sup 59/Co neutron cross sections between 3 and 50 MeV
Calculation of /sup 59/Co neutron cross sections between 3 and 50 MeV Open
Knowledge of the /sup 59/Co(n,p), (n,..cap alpha..), and (n,xn) cross sections up to 50 MeV are necessary to satisfy priority dosimetry data needs of the FMIT facility. Since experimental data extend only to 25 MeV in the case of (n,xn) re…