Industrial safety studies for VVERs in FRAMATOME
Description
Since more than ten years, FRAMATOME has been involved in VVER activities, initiated by a comparison of Western and VVER plants, in the frame of a commercial proposal to Finnish customers in the early 80s. FRAMATOME is funding together with EDF and IPSN the development of the advanced thermalhydraulic code CATHARE. Currently available versions of CATHARE allow to perform best estimate calculations of LOCA accidents, small and large breaks, and non LOCA transients such as steam generator feedwater or steam line breaks, partial or total feedwater loss, steam generator tube ruptures, and other transients. CATHARE is used at FRAMATOME for all these transients in the frame of advanced methodologies for safety analysis, or for reference calculations. (au). (20 figs., 2 tabs.)
Additional details
Publishing Information
- ISBN
- 951-763-880-9
- Imprint Title
- French-Finnish colloquium on safety of French and Russian type nuclear power plants
- Imprint Pagination
- 286 p.
- Journal Page Range
- p. 18-40.
- Report number
- LTKK-TJ--41
Conference
- Title
- Seminar on French-Finnish colloquium on safety of French and Russian type nuclear power plants.
- Dates
- 14-16 Jun 1994.
- Place
- Lappeenranta (Finland).
INIS
- Country of Publication
- Finland
- Country of Input or Organization
- Finland
- INIS RN
- 26047595
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; COMPUTERIZED SIMULATION; LOSS OF COOLANT; REACTOR COOLING SYSTEMS; REACTOR SAFETY; SAFETY ANALYSIS; TRANSIENTS; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS