Published September 1997
| Version v1
Report
Safety analyses for the new fuel at the Dukovany NPP. Feedwater line break. Revision 1
Description
An accident associated with feedwater line break within the segment between the check valve and the steam generator (within the hermetic confinement) was analyzed in the context of preparation for transition to the new fuel at Dukovany. Two analyzes were processed: the one was oriented to the most adverse reactor core cooling, the other, to the maximum primary pressure. The RELAP5/MOD3.1 code was used. The results give evidence that the acceptance criteria of the design basis accident were met
Availability note (English)
Available from Nuclear Research Institute Rez, 250 68 Rez, Czech RepublicAdditional details
Additional titles
- Original title (Czech)
- Bezpecnostni analyzy pro nove palivo JE Dukovany - prasknuti potrubi napajeci vody. Revize c. 1
Publishing Information
- Imprint Pagination
- 146 p.
- Report number
- UJV--11002-T
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 30058544
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- COOLING; DESIGN BASIS ACCIDENTS; FEEDWATER; PIPES; R CODES; REACTOR CORES; RUPTURES; SAFETY ANALYSIS; STEAM GENERATORS
- Descriptors DEC
- ACCIDENTS; BOILERS; COMPUTER CODES; FAILURES; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTOR COMPONENTS; VAPOR GENERATORS; WATER
Optional Information
- Notes
- 62 figs., 18 refs.