Published 1976
| Version v1
Report
Open
FLATT - a computer programme for calculating flow and temperature transients in nuclear fuels
- 1. Bhabha Atomic Research Centre, Bombay (India). Reactor Engineering Div.
Description
FLATT is a computer code written in Fortran language for BESM-6 computer. The code calculates the flow transients in the coolant circuit of a nuclear reactor, caused by pump failure, and the consequent temperature transients in the fuel, clad, and the coolant. In addition any desired flow transient can be fed into the programme and the resulting temperature transients can be calculated. A case study is also presented. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
8313651.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 10 p.
- Report number
- INIS-mf--3475
Conference
- Title
- 3. national heat and mass transfer conference.
- Dates
- 11 Dec 1975.
- Place
- Bombay, India.
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 8313651
- Subject category
- S99: GENERAL AND MISCELLANEOUS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLANTS; F CODES; FLUID FLOW; FUEL ELEMENTS; LOSS OF FLOW; PUMPS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; TEMPERATURE NOISE; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; NOISE; REACTOR COMPONENTS