Published December 2003 | Version v1
Report Metadata-only

Coolant temperature field in the inlet section of the VVER 1000 reactor. Rev. 1

Creators

Description

The results of calculation are given of the coolant temperature field development at the entrance to the reactor core for 2 typical accidents, viz. steam line break for the adjacent/counter-current loops with failure of one main coolant pump. The effect of the secondary flow in the inlet reactor sleeves on the coolant temperature field was assessed. The calculations and models follow up work done in 2002. The input data were obtained and analyses performed by using a new version of the FLUENT 6 code. (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)
Teplotni pole chladiciho media ve vstupnim traktu reaktoru VVER 1000. Revize 1

Publishing Information

Imprint Pagination
[134 p.]
Report number
UJV--11977-T

INIS

Country of Publication
Czech Republic
Country of Input or Organization
Czech Republic
INIS RN
38016006
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; COOLANTS; F CODES; HYPOTHETICAL ACCIDENTS; PIPE FITTINGS; PRIMARY COOLANT CIRCUITS; REACTOR CORES; RUPTURES; STEAM LINES; TEMPERATURE DISTRIBUTION; WWER TYPE REACTORS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FAILURES; PIPELINES; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
16 tabs., 43 figs., 4 refs.