Published May 17, 2001 | Version v1
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HORIZONTAL LIFTING OF 5 DHLW/DOE LONG, 12-PWR LONG AND 24-BWR WASTE PACKAGES

Description

The objective of this calculation was to determine the structural response of a 12-Pressurized Water Reactor (PWR) Long, a 24-Boiling Water Reactor (BWR) and a 5-Defense High Level Waste/Department of Energy (DHLW/DOE)--Long spent nuclear fuel waste packages lifted in a horizontal position. The scope of this calculation was limited to reporting the calculation results in terms of maximum stress intensities in the trunnion collar sleeves. In addition, the maximum stress intensities in the inner and outer shells of the waste packages were presented for illustrative purposes. The information provided by the sketches (Attachments I, II and III) is that of the potential design of the types of waste packages considered in this calculation, and all obtained results are valid for these designs only. This calculation is associated with the waste package design and was performed by the Waste Package Design Section in accordance with the ''Technical work plan for: Waste Package Design Description for LA'' (Ref. 7). AP-3.12Q, Calculations (Ref. 13), was used to perform the calculation and develop the document

Availability note (English)

Available from INIS in electronic form; Also available from OSTI as DE00888846; PURL: https://www.osti.gov/servlets/purl/888846-hDjGD7/

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Additional details

Publishing Information

Imprint Pagination
37 p.
Report number
CAL-EBS-ME--000010

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
38002384
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Descriptors DEI
DESIGN; NUCLEAR FUELS; SLEEVES; SPENT FUELS; WASTES; WATER
Descriptors DEC
ENERGY SOURCES; FUELS; HYDROGEN COMPOUNDS; MATERIALS; NUCLEAR FUELS; OXYGEN COMPOUNDS; REACTOR MATERIALS

Optional Information