Published August 1977
| Version v1
Report
Open
Preliminary model for core/concrete interactions
Description
A preliminary model is described for computing the rate of penetration of concrete by a molten LWR core. Among the phenomena included are convective stirring of the melt by evolved gases, admixture of concrete decomposition products to the melt, chemical reactions, radiative heat loss, and variation of heat transfer coefficients with local pressure. The model is most applicable to a two-phase melt (metallic plus oxidic) having a fairly high metallic content
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.Files
9357800.pdf
Files
(515.3 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:cca02d4e3de5f261a6eb162786a901aa
|
515.3 kB | Preview Download |
Additional details
Additional titles
- Augmented title (English)
- PWR and BWR
Publishing Information
- Imprint Pagination
- 45 p.
- Report number
- SAND--77-0370
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9357800
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ABLATION; BWR TYPE REACTORS; CONCRETES; CONTAINMENT SHELLS; CORIUM; HEAT TRANSFER; MATHEMATICAL MODELS; MECHANICAL PROPERTIES; MELTDOWN; MOLTEN METAL-WATER REACTIONS; PWR TYPE REACTORS; REACTOR SAFETY; THERMAL STRESSES
- Descriptors DEC
- ACCIDENTS; BUILDING MATERIALS; CONTAINMENT; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTORS; SAFETY; STRESSES; WATER COOLED REACTORS; WATER MODERATED REACTORS