Published August 1995
| Version v1
Miscellaneous
Restricted
CONTAIN calculations
Creators
Description
In the first phase of a benchmark comparison, the CONTAIN code was used to calculate an assumed EPR accident 'medium-sized leak in the cold leg', especially for the first two days after initiation of the accident. The results for global characteristics compare well with those of FIPLOC, MELCOR and WAVCO calculations, if the same materials data are used as input. However, significant differences show up for local quantities such as flows through leakages. (orig.)
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Additional titles
- Original title (German)
- CONTAIN-Rechnungen
Publishing Information
- Imprint Title
- Karlsruhe Research Center, Nuclear Safety Research Project (PSF). Annual report 1994
- Imprint Pagination
- 433 p.
- Journal Page Range
- p. 227-233.
- ISSN
- 0947-8620
- Report number
- FZKA--5600
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 28005670
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; CONTAINMENT; FORSCHUNGSZENTRUM KARLSRUHE; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; GERMAN FR ORGANIZATIONS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Forschungszentrum Karlsruhe, Projekt Nukleare Sicherheitsforschung. Jahrsbericht 1994.