完整後設資料紀錄
DC 欄位 | 值 | 語言 |
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dc.contributor.author | Yang, Shaw-Yang | en_US |
dc.contributor.author | Yeh, Hund-Der | en_US |
dc.date.accessioned | 2014-12-08T15:08:41Z | - |
dc.date.available | 2014-12-08T15:08:41Z | - |
dc.date.issued | 2009-09-30 | en_US |
dc.identifier.issn | 0304-3894 | en_US |
dc.identifier.uri | http://dx.doi.org/10.1016/j.jhazmat.2009.03.068 | en_US |
dc.identifier.uri | http://hdl.handle.net/11536/6650 | - |
dc.description.abstract | The heat of high-level nuclear waste maybe generated and released from a canister at final disposal sites. The waste heat may affect the engineering properties of waste canisters, buffers, and backfill material in the emplacement tunnel and the host rock. This study addresses the problem of the heat generated from the waste canister and analyzes the heat distribution between the buffer and the host rock, which is considered as a radial two-layer heat flux problem. A conceptual model is first constructed for the heat conduction in a nuclear waste repository and then mathematical equations are formulated for modeling heat flow distribution at repository sites. The Laplace transforms are employed to develop a solution for the temperature distributions in the buffer and the host rock in the Laplace domain, which is numerically inverted to the time-domain solution using the modified Crump method. The transient temperature distributions for both the single- and multi-borehole cases are simulated in the hypothetical geological repositories of nuclear waste. The results show that the temperature distributions in the thermal field are significantly affected by the decay heat of the waste canister, the thermal properties of the buffer and the host rock, the disposal spacing, and the thickness of the host rock at a nuclear waste repository. (C) 2009 Elsevier B.V. All rights reserved. | en_US |
dc.language.iso | en_US | en_US |
dc.subject | Geological repository | en_US |
dc.subject | High-level nuclear waste | en_US |
dc.subject | Heat transfer | en_US |
dc.subject | Analytical solution | en_US |
dc.title | Modeling transient heat transfer in nuclear waste repositories | en_US |
dc.type | Article | en_US |
dc.identifier.doi | 10.1016/j.jhazmat.2009.03.068 | en_US |
dc.identifier.journal | JOURNAL OF HAZARDOUS MATERIALS | en_US |
dc.citation.volume | 169 | en_US |
dc.citation.issue | 1-3 | en_US |
dc.citation.spage | 108 | en_US |
dc.citation.epage | 112 | en_US |
dc.contributor.department | 環境工程研究所 | zh_TW |
dc.contributor.department | Institute of Environmental Engineering | en_US |
dc.identifier.wosnumber | WOS:000268967200015 | - |
dc.citation.woscount | 1 | - |
顯示於類別: | 期刊論文 |