Published 1989 | Version v1
Report Open

Cask drop testing and analysis

Description

Packages designed to carry spent fuel within the United States must be approved and certified by the Nuclear Regulatory Commission (NRC). This is done by submitting an application to the NRC that describes the package design and provides a detailed technical evaluation of its performance under a variety of normal and accident conditions. These technical evaluations are often based on a combination of theoretical analysis and experimental testing that can be particularly important if it is necessary to corroborate specific analytical assumptions or confirm the methodology used. Tests can be applied to full-scale prototypes or scale model packages, either of which can frequently provide the necessary evidence to substantiate the conclusions. This report discusses two types of packages that were tested at the Oak Ridge National Laboratory -- a scale model spent fuel cask and a full-scale canister designed to be carried inside a spent fuel cask. They were designed by two private companies. Both companies applied to the NRC for a Certificate of Compliance for their casks. In both cases, the combination of testing and analysis, and the way it was applied, formed a critical part of their application. 7 refs., 2 figs., 1 tab

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 - OSTI; 1 as DE89008921.

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Additional details

Publishing Information

Imprint Pagination
5 p.
Report number
CONF-890721--14

Conference

Title
Joint ASME/JSME pressure vessel and piping conference.
Dates
23-27 Jul 1989.
Place
Honolulu, HI (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
20069125
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CASKS; EVALUATION; HIGH-LEVEL RADIOACTIVE WASTES; IMPACT STRENGTH; IMPACT TESTS; LICENSING PROCEDURES; SPECIFICATIONS; TESTING; TRANSPORT; US NRC
Descriptors DEC
ADMINISTRATIVE PROCEDURES; CONTAINERS; MATERIALS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; NATIONAL ORGANIZATIONS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; US ORGANIZATIONS; WASTES

Optional Information

Notes
Portions of this document are illegible in microfiche products.