Experimental cross section for the 139La(n, γ)140La reaction at 0.0536 eV

Measurement of cross section of the 98Mo(n, γ)99Mo reaction using monochromatic thermal neutrons

“…The standard cross section of the monitor reaction 197 Au( , ) 198 Au at the investigated energies was evaluated from the experimental data reported by Yamamoto et al [20], Pavlenko and Gnidak [21], Haddad et al [22] and the data reported in ENDF/B-VII [23] library by a fitting procedure. The values obtained are Brought to you by | New York University Bobst Library Technical Services Authenticated Download Date | 6/1/15 1:30 PM [10]. No activity was found in the Au-foil covered by Cd and that indicated the absence of epithermal neutrons.…”

“…The method of measurement at those two energies has been well established in our laboratory and good results were obtained for several reactions [10][11][12][13][14]. Thereafter, the values measured at those two energies should be extrapolated to obtain values at 0.0253 eV.…”

Experimental cross section for the 152Sm(n, γ)153Sm reaction at 0.0334 eV

“…The standard cross section of the 197 Au( , ) 198 Au reaction at the above energy was evaluated from the experimental data reported Brought to you by | New York University Bobst Library Technical Services Authenticated Download Date | 6/1/15 12:57 PM by Yamamoto et al [17], Pavlenko et al [18], Haddad et al [19] and the data reported in ENDF/B-VII [20] library by a fitting procedure. Chowdhury et al have described a detailed evaluation of the monitor reaction cross section [13]. = exp(− ) (1) where, is the incident flux and is the flux of neutron at exit of sample matrix of a thickness, .…”

“…[2][3][4][5][6][7][8][9][10][11][12]. Uddin et al described in detail the measurement of the neutron capture cross sections for several targets at 0.0536 eV for the first time [13][14][15][16]. The same method has been applied in this work.…”

Measurement of cross-section for the 139La(n,γ)140la reaction using reflected neutron beam at 0.0334 eV energy

“…More over, ac cu rate mea surements of neu tron cap ture cross-sec tions for a large number of nuclides, at the ther mal en ergy re gion, are currently of great im por tance in neu tron trans port cal cu la tions and in re ac tor safety as sess ments. A number of au thors have re ported ther mal neu tron cap ture cross-sec tions on 139 La mostly at av er age ther mal neutron en ergy of 0.0253 eV [5][6][7][8][9][10][11][12][13][14][15][16][17][18][19][20] and there are dis crepan cies among the data (8.1 to 9.5 b, where 1 b = 1×10 -28 m 2 , dif fer by about 17 %). In most of these stud ies, thermal neu tron cross-sec tions were de ter mined ex per imen tally by the ac ti va tion method us ing cad mium cut-off en ergy tech nique.…”