Waste Package Lifting Calculation

Marr, H.

United States. Department of Energy. Yucca Mountain Project Office.

关键词: Response Functions;    Radioactive Wastes;    Materials Handling;    Spent Fuel Casks;    42 Engineering;   

DOI  :  10.2172/893834
RP-ID  :  CAL-EBS-ME-00007, Rev. 01
RP-ID  :  NA
RP-ID  :  893834

美国|英语

来源: UNT Digital Library

【 摘 要 】

The objective of this calculation is to evaluate the structural response of the waste package during the horizontal and vertical lifting operations in order to support the waste package lifting feature design. The scope of this calculation includes the evaluation of the 21 PWR UCF (pressurized water reactor uncanistered fuel) waste package, naval waste package, 5 DHLW/DOE SNF (defense high-level waste/Department of Energy spent nuclear fuel)--short waste package, and 44 BWR (boiling water reactor) UCF waste package. Procedure AP-3.12Q, Revision 0, ICN 0, calculations, is used to develop and document this calculation.