Integrated decay heat load method to analyze repository capacity impact of a fuel cycle

Cited 1 time in webofscience Cited 0 time in scopus
  • Hit : 333
  • Download : 0
Assessing the needs for repository capacity from nuclear waste disposal is essential for fuel cycle development or repository development planning. As the repository capacity is mainly constrained by thermal design limits on the repository rocks, a detailed mountain-scale heat transfer calculation is needed for repository capacity impact analysis. In this paper, a simplified repository capacity impact analysis method is proposed as an alternative to performing repository scale heat transfer analysis. The method is based on the use of integrated decay heat load (IDHL) limits. The derived integrated decay heat loads were found to appropriately represent the drift wall temperature limit (200 degrees C) and the midway between adjacent drifts temperature limit (96 degrees C) under the high temperature operating mode as long as the wastes are uniformly loaded into the repository. Results indicated that the long-term integrated decay heat load (IDHL(L)) and the short-term integrated decay heat load (IDHL(S)) can be effectively used to represent the repository capacity impact for SNFs and HLWs, respectively. Comparisons indicated good agreement between the proposed IDHL method and the repository heat transfer analysis-based approach. Published by Elsevier Ltd.
Publisher
PERGAMON-ELSEVIER SCIENCE LTD
Issue Date
2009-09
Language
English
Article Type
Article
Citation

ANNALS OF NUCLEAR ENERGY, v.36, no.9, pp.1366 - 1373

ISSN
0306-4549
DOI
10.1016/j.anucene.2009.06.015
URI
http://hdl.handle.net/10203/101834
Appears in Collection
NE-Journal Papers(저널논문)
Files in This Item
There are no files associated with this item.
This item is cited by other documents in WoS
⊙ Detail Information in WoSⓡ Click to see webofscience_button
⊙ Cited 1 items in WoS Click to see citing articles in records_button

qr_code

  • mendeley

    citeulike


rss_1.0 rss_2.0 atom_1.0