Abstract
The performance of the SKB copper/steel canister has been analyzed. The present knowledge of long-term function of the canister is summarized. Radionuclide release calculations for a reference failure scenario and the effect of some variations on release rates are shown. The Features, Events and Processes (FEPs) that are affecting the studied scenarios have been classified according to the `Rock Engineering Systems` methodology as defined by SKB for the copper/steel canister. Radionuclide release rate is calculated for a reference failure scenario where a small hole in the weld of the outer copper overpack is assumed to exist at the time of deposition. The hole in the copper overpack is assumed to be of a constant size until the inner steel canister looses its mechanical integrity. The steel is assumed to maintain mechanical stability during 5000 years and after this time period the hole through the copper is assumed to be 0.1 m{sup 2}, which translate to insignificant transport resistance from the canister wall. The release rates for C-14, Sr-90, I-129, Cs-137, Pu-239 and Am-241 are calculated for the reference failure scenario and for a number of variations. The variations include glaciation, only few of the Zircaloy tubes damaged, different canister filling
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Citation Formats
Widen, H, and Sellin, P.
Performance of the SKB copper/steel canister.
Sweden: N. p.,
1994.
Web.
Widen, H, & Sellin, P.
Performance of the SKB copper/steel canister.
Sweden.
Widen, H, and Sellin, P.
1994.
"Performance of the SKB copper/steel canister."
Sweden.
@misc{etde_10112228,
title = {Performance of the SKB copper/steel canister}
author = {Widen, H, and Sellin, P}
abstractNote = {The performance of the SKB copper/steel canister has been analyzed. The present knowledge of long-term function of the canister is summarized. Radionuclide release calculations for a reference failure scenario and the effect of some variations on release rates are shown. The Features, Events and Processes (FEPs) that are affecting the studied scenarios have been classified according to the `Rock Engineering Systems` methodology as defined by SKB for the copper/steel canister. Radionuclide release rate is calculated for a reference failure scenario where a small hole in the weld of the outer copper overpack is assumed to exist at the time of deposition. The hole in the copper overpack is assumed to be of a constant size until the inner steel canister looses its mechanical integrity. The steel is assumed to maintain mechanical stability during 5000 years and after this time period the hole through the copper is assumed to be 0.1 m{sup 2}, which translate to insignificant transport resistance from the canister wall. The release rates for C-14, Sr-90, I-129, Cs-137, Pu-239 and Am-241 are calculated for the reference failure scenario and for a number of variations. The variations include glaciation, only few of the Zircaloy tubes damaged, different canister filling materials, variations in sorption properties of the bentonite clay and different life-time of the inner steel canister. The performance of the canister and near-field, concerning the release rates of the studied radionuclides, is as expected, comparable to the release rates obtained in SKB 91. 11 refs, figs, tabs.}
place = {Sweden}
year = {1994}
month = {Sep}
}
title = {Performance of the SKB copper/steel canister}
author = {Widen, H, and Sellin, P}
abstractNote = {The performance of the SKB copper/steel canister has been analyzed. The present knowledge of long-term function of the canister is summarized. Radionuclide release calculations for a reference failure scenario and the effect of some variations on release rates are shown. The Features, Events and Processes (FEPs) that are affecting the studied scenarios have been classified according to the `Rock Engineering Systems` methodology as defined by SKB for the copper/steel canister. Radionuclide release rate is calculated for a reference failure scenario where a small hole in the weld of the outer copper overpack is assumed to exist at the time of deposition. The hole in the copper overpack is assumed to be of a constant size until the inner steel canister looses its mechanical integrity. The steel is assumed to maintain mechanical stability during 5000 years and after this time period the hole through the copper is assumed to be 0.1 m{sup 2}, which translate to insignificant transport resistance from the canister wall. The release rates for C-14, Sr-90, I-129, Cs-137, Pu-239 and Am-241 are calculated for the reference failure scenario and for a number of variations. The variations include glaciation, only few of the Zircaloy tubes damaged, different canister filling materials, variations in sorption properties of the bentonite clay and different life-time of the inner steel canister. The performance of the canister and near-field, concerning the release rates of the studied radionuclides, is as expected, comparable to the release rates obtained in SKB 91. 11 refs, figs, tabs.}
place = {Sweden}
year = {1994}
month = {Sep}
}