Abstract
The Reactor Theory Division of the AEC has been contracted by ESKOM (South Africa) to prepare cross section data for the surveillance specimens as part of the overall reactor vessel surveillance (RVS) program. Spectrum averaged one energy group cross sections for the Cu{sub 63}(n,{alpha}), Ni{sub 58}(n,p), Fe{sub 54}(n,p), U{sub 238}(n,f) and Np{sub 237}(n,f) reactions, has been defined. These cross sections were then used in conjunction with dosimetry measurements to obtain preliminary estimates of the fluence exposure of the surveillance specimens. The basic calculational procedure employed to obtain the spectrum averaged cross sections in the position of the capsule (outside the thermal pads) and the spectrum averaged cross sections are given. A sensitivity analysis of several parameters is involved with a view to determine a suitable error bound for the spectrum averaged cross sections. Comparisons are made with the literature and final conclusions are drawn and some perspective on future calculations is given. 2 figs., 3 tabs., 16 refs.
Citation Formats
Stoker, C C.
The preparation of cross section data for the ESKOM Koeberg reactor vessel surveillance capsule program.
South Africa: N. p.,
1991.
Web.
Stoker, C C.
The preparation of cross section data for the ESKOM Koeberg reactor vessel surveillance capsule program.
South Africa.
Stoker, C C.
1991.
"The preparation of cross section data for the ESKOM Koeberg reactor vessel surveillance capsule program."
South Africa.
@misc{etde_10139794,
title = {The preparation of cross section data for the ESKOM Koeberg reactor vessel surveillance capsule program}
author = {Stoker, C C}
abstractNote = {The Reactor Theory Division of the AEC has been contracted by ESKOM (South Africa) to prepare cross section data for the surveillance specimens as part of the overall reactor vessel surveillance (RVS) program. Spectrum averaged one energy group cross sections for the Cu{sub 63}(n,{alpha}), Ni{sub 58}(n,p), Fe{sub 54}(n,p), U{sub 238}(n,f) and Np{sub 237}(n,f) reactions, has been defined. These cross sections were then used in conjunction with dosimetry measurements to obtain preliminary estimates of the fluence exposure of the surveillance specimens. The basic calculational procedure employed to obtain the spectrum averaged cross sections in the position of the capsule (outside the thermal pads) and the spectrum averaged cross sections are given. A sensitivity analysis of several parameters is involved with a view to determine a suitable error bound for the spectrum averaged cross sections. Comparisons are made with the literature and final conclusions are drawn and some perspective on future calculations is given. 2 figs., 3 tabs., 16 refs.}
place = {South Africa}
year = {1991}
month = {Jan}
}
title = {The preparation of cross section data for the ESKOM Koeberg reactor vessel surveillance capsule program}
author = {Stoker, C C}
abstractNote = {The Reactor Theory Division of the AEC has been contracted by ESKOM (South Africa) to prepare cross section data for the surveillance specimens as part of the overall reactor vessel surveillance (RVS) program. Spectrum averaged one energy group cross sections for the Cu{sub 63}(n,{alpha}), Ni{sub 58}(n,p), Fe{sub 54}(n,p), U{sub 238}(n,f) and Np{sub 237}(n,f) reactions, has been defined. These cross sections were then used in conjunction with dosimetry measurements to obtain preliminary estimates of the fluence exposure of the surveillance specimens. The basic calculational procedure employed to obtain the spectrum averaged cross sections in the position of the capsule (outside the thermal pads) and the spectrum averaged cross sections are given. A sensitivity analysis of several parameters is involved with a view to determine a suitable error bound for the spectrum averaged cross sections. Comparisons are made with the literature and final conclusions are drawn and some perspective on future calculations is given. 2 figs., 3 tabs., 16 refs.}
place = {South Africa}
year = {1991}
month = {Jan}
}