Published November 1980
| Version v1
Report
Open
Nuclear criticality safety studies applicable to spent fuel shipping cask designs and spent fuel storage
Description
Criticality analyses of water-moderated and reflected arrays of LWR fresh and spent fuel assemblies were carried out in this study. The calculated results indicate that using the assumption of fresh fuel loading in spent fuel shipping cask design leads to assembly spacings which are about twice the spacings of spent fuel loadings. Some shipping cask walls of composite lead and water are more effective neutron reflectors than water of 30.48 cm
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.Files
12585530.pdf
Files
(474.5 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:1bed77526efe50828ed5c12e6d6cec81
|
474.5 kB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 28 p.
- Report number
- ORNL/TM--7403
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12585530
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- CASKS; CRITICALITY; FUEL ASSEMBLIES; FUEL CYCLE; LEAD; NEUTRON REFLECTORS; SAFETY; SPENT FUEL ELEMENTS; WATER; WATER COOLED REACTORS
- Descriptors DEC
- CONTAINERS; ELEMENTS; FUEL ELEMENTS; HYDROGEN COMPOUNDS; METALS; OXYGEN COMPOUNDS; REACTOR COMPONENTS; REACTORS