Published 1985
| Version v1
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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
17073468.pdf
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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.