Published 1985 | Version v1
Report Open

ASTRA code for thermal mode calculation of a fuel cluster with coaxial turbular elements

Description

The description and text of the ASTRA code for thermal calculation of a coaxial tubular fuel element cluster inserted into the Field type channel or direct - flow channel are given. The code is written in FORTRAN and permits to calculate the distribution of heat fluxes from fuel element surfaces, temperatures of a coolant in gaps between them, temperatures of external surfaces of fuel elements, temperatures of contact of fuel pellets with cladding and maximum rod temperatures along the core length

Availability note (English)

MF available from INIS under the Report Number.

Files

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Additional details

Additional titles

Original title (Russian)
Программа ASTRA для расчета теплового режима TVS с трубчатыми коаксиальными твэлами

Publishing Information

Imprint Pagination
19 p.
Report number
IAE--4112/4

INIS

Country of Publication
USSR
Country of Input or Organization
USSR
INIS RN
17073468
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
A CODES; ALGORITHMS; FORTRAN; HEAT FLUX; HOLLOW FUEL RODS; TEMPERATURE DEPENDENCE; TEMPERATURE DISTRIBUTION
Descriptors DEC
COMPUTER CODES; FUEL ELEMENTS; FUEL RODS; PROGRAMMING LANGUAGES; REACTOR COMPONENTS

Optional Information

Notes
3 figs.; 4 tabs.