Published December 2003 | Version v1
Report Metadata-only

Analysis of a LOCA 2xD233 in sealed compartments of the Dukovany nuclear power plant

Creators

Description

The report presents calculations of Dukovany nuclear power plant sealed compartments response to loss-of-coolant accident in case of double-ended break of pipe from the safety injection tank. The calculations were performed with MELCOR 1.8.5 code. Mainly parameters on the reactor pressure vessel external surface in case of reactor pit flooding are monitored. Results will be used as input for the structural analysis of pressurized thermal shocks of reactor pressure vessel. (author)

Availability note (English)

Available (also in the electronic format as a PDF reproduction) from Nuclear Research Institute Rez, 250 68 Rez, Czech Republic; e-mail contact: ret@nri.cz, ric@nri.cz

Additional details

Additional titles

Original title (Czech)
Vypocty nehody LOCA 2xD233 v hermetickych prostorech Elektrarny Dukovany

Publishing Information

Imprint Pagination
[140 p.]
Report number
UJV--11993-T

INIS

Country of Publication
Czech Republic
Country of Input or Organization
Czech Republic
INIS RN
38016014
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; DUKOVANY-1 REACTOR; HYPOTHETICAL ACCIDENTS; LOSS OF COOLANT; M CODES; PIPES; PRESSURE VESSELS; RUPTURES
Descriptors DEC
ACCIDENTS; COMPUTER CODES; CONTAINERS; ENRICHED URANIUM REACTORS; FAILURES; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS

Optional Information

Notes
Developed within the Dukovany NPP project 'Methodological and technological approaches to the safety of VVER nuclear power plants'. 9 tabs., 98 figs., 33 refs.