Published September 1987
| Version v1
Report
Calculation of the first APWR-experiment with the FLUT code
Creators
Description
For the analysis of the refill and reflood phases of the LOCA the FLUT code was modified: new correlations to evaluate the friction losses in an APWR geometry (as in the modified RELAP5) and a new model for the droplet diameter in the region just above the quench front were introduced. The KfK-version of the program was tested by means of the post-test analysis of reflood experiments in both PWR (FLECHT and SEFLEX facilities) and APWR (FLORESTAN facility) bundles. (orig./DG)
Additional details
Additional titles
- Original title (German)
- Vorausberechnung des ersten FDWR-Flutexperimentes mit dem FLUT-Rechenprogramm
Publishing Information
- Imprint Title
- Nuclear Safety Project. Annual report 1986
- Imprint Pagination
- 358 p.
- Journal Page Range
- p. 4100-68-4100-78.
- Report number
- KFK--4100
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 19068769
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CORE FLOODING SYSTEMS; DIFFERENTIAL EQUATIONS; F CODES; FRICTION; LOSS OF COOLANT; PWR TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ECCS; ENRICHED URANIUM REACTORS; EQUATIONS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Projekt Nukleare Sicherheit. Jahresbericht 1986.