Abstract
The average cross section in the {sup 235} U fission spectrum has been measured by the activation technique, for the following thresholds reactions: {sup 115} In(n,n`) {sup 115m} In, {sup 232} Th(n,f) P.F., {sup 46{sup ,}47{sup ,}48} Ti(n,p) {sup 46,47{sup ,}48} Sc, {sup 55} Mn(n,2 n){sup 54} Mn, {sup 51} V(n,{alpha}){sup 48} Sc, {sup 90} Zr(n,2 n){sup 89} Zr, {sup 93} Nb(n,2 n){sup 92m} Nb, {sup 58} Ni(n,2 n){sup 57} Ni, {sup 24} Mg(n,p){sup 24} Na, {sup 56} Fe(n,p){sup 56} Mn, {sup 59} Co(n,{alpha}){sup 56} Mn and {sup 63} Cu(n,{alpha}){sup 60} Co. The activation foils were irradiated close ({approx} 4 mm) to the core of the IEA-R1 research reactor in the IPEN-CNEN/SP. The reactor was operated at 2 MW yielding a fast neutron flux around 5 x 10{sup 12} n.cm{sup -2}. s{sup -1}. The neutron flux density was monitored by activation reactions with well known averaged cross sections and with effective thresholds above 1 MeV. The foil activities were measured in a calibrated HPGe spectrometer. The neutron spectrum has been calculated using the SAIPS unfolding system applied to the activation data. A detailed error analysis was performed using the covariance matrix methodology. The results were compared with those from other
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Citation Formats
Maidana, N L.
Average cross section measurements in U-235 fission neutron spectrum for some threshold reactions; Medidas de seccoes de choque medias no espectro de fissao do U-235 para algumas reacoes de limiar.
Brazil: N. p.,
1993.
Web.
Maidana, N L.
Average cross section measurements in U-235 fission neutron spectrum for some threshold reactions; Medidas de seccoes de choque medias no espectro de fissao do U-235 para algumas reacoes de limiar.
Brazil.
Maidana, N L.
1993.
"Average cross section measurements in U-235 fission neutron spectrum for some threshold reactions; Medidas de seccoes de choque medias no espectro de fissao do U-235 para algumas reacoes de limiar."
Brazil.
@misc{etde_10157169,
title = {Average cross section measurements in U-235 fission neutron spectrum for some threshold reactions; Medidas de seccoes de choque medias no espectro de fissao do U-235 para algumas reacoes de limiar}
author = {Maidana, N L}
abstractNote = {The average cross section in the {sup 235} U fission spectrum has been measured by the activation technique, for the following thresholds reactions: {sup 115} In(n,n`) {sup 115m} In, {sup 232} Th(n,f) P.F., {sup 46{sup ,}47{sup ,}48} Ti(n,p) {sup 46,47{sup ,}48} Sc, {sup 55} Mn(n,2 n){sup 54} Mn, {sup 51} V(n,{alpha}){sup 48} Sc, {sup 90} Zr(n,2 n){sup 89} Zr, {sup 93} Nb(n,2 n){sup 92m} Nb, {sup 58} Ni(n,2 n){sup 57} Ni, {sup 24} Mg(n,p){sup 24} Na, {sup 56} Fe(n,p){sup 56} Mn, {sup 59} Co(n,{alpha}){sup 56} Mn and {sup 63} Cu(n,{alpha}){sup 60} Co. The activation foils were irradiated close ({approx} 4 mm) to the core of the IEA-R1 research reactor in the IPEN-CNEN/SP. The reactor was operated at 2 MW yielding a fast neutron flux around 5 x 10{sup 12} n.cm{sup -2}. s{sup -1}. The neutron flux density was monitored by activation reactions with well known averaged cross sections and with effective thresholds above 1 MeV. The foil activities were measured in a calibrated HPGe spectrometer. The neutron spectrum has been calculated using the SAIPS unfolding system applied to the activation data. A detailed error analysis was performed using the covariance matrix methodology. The results were compared with those from other authors. (author).}
place = {Brazil}
year = {1993}
month = {Dec}
}
title = {Average cross section measurements in U-235 fission neutron spectrum for some threshold reactions; Medidas de seccoes de choque medias no espectro de fissao do U-235 para algumas reacoes de limiar}
author = {Maidana, N L}
abstractNote = {The average cross section in the {sup 235} U fission spectrum has been measured by the activation technique, for the following thresholds reactions: {sup 115} In(n,n`) {sup 115m} In, {sup 232} Th(n,f) P.F., {sup 46{sup ,}47{sup ,}48} Ti(n,p) {sup 46,47{sup ,}48} Sc, {sup 55} Mn(n,2 n){sup 54} Mn, {sup 51} V(n,{alpha}){sup 48} Sc, {sup 90} Zr(n,2 n){sup 89} Zr, {sup 93} Nb(n,2 n){sup 92m} Nb, {sup 58} Ni(n,2 n){sup 57} Ni, {sup 24} Mg(n,p){sup 24} Na, {sup 56} Fe(n,p){sup 56} Mn, {sup 59} Co(n,{alpha}){sup 56} Mn and {sup 63} Cu(n,{alpha}){sup 60} Co. The activation foils were irradiated close ({approx} 4 mm) to the core of the IEA-R1 research reactor in the IPEN-CNEN/SP. The reactor was operated at 2 MW yielding a fast neutron flux around 5 x 10{sup 12} n.cm{sup -2}. s{sup -1}. The neutron flux density was monitored by activation reactions with well known averaged cross sections and with effective thresholds above 1 MeV. The foil activities were measured in a calibrated HPGe spectrometer. The neutron spectrum has been calculated using the SAIPS unfolding system applied to the activation data. A detailed error analysis was performed using the covariance matrix methodology. The results were compared with those from other authors. (author).}
place = {Brazil}
year = {1993}
month = {Dec}
}