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.Files
20069125.pdf
Files
(296.5 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:995b8fdccb7ee476bd9fa533592d1f03
|
296.5 kB | Preview Download |
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.