Published 1984
| Version v1
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Heat Transfer treatment in computer codes for safety analysis
Description
Increased number of operating nuclear power plants has stressed importance of nuclear safety evaluation. For this reason, accordingly to regulatory commission request, safety analyses with computer codes are preformed. In this paper part of this thermohydraulic models dealing with wall-to-fluid heat transfer correlations in computer codes TRAC=PF1, RELAP4/MOD5, RELAP5/MOD1 and COBRA-IV is discussed. (author)
Availability note (English)
Available from INIS in electronic form; Also available from the Institute of Nuclear Sciences VINCAFiles
38033190.pdf
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Additional details
Additional titles
- Original title (Slovenian)
- Obravnanje prenosa toplote v racunalniskim programih za varnosne analize
Publishing Information
- Publisher
- Society for Electronics,Telecommunications, Automation, and Nuclear Engineering
- Imprint Place
- Belgrade (Yugoslavia)
- Imprint Pagination
- 8 p.
- Report number
- INIS-RS--0742
Conference
- Title
- Consulting Meeting on Introducing nuclear power in Yugoslavia
- Original Conference Title
- Zbornik radova 28. Konferencija za ETAN VI sveska
- Acronym
- 28. Conference - ETAN '84
- Dates
- 4-8 Jun 1984
- Place
- Split (Yugoslavia)
INIS
- Country of Publication
- Yugoslavia
- Country of Input or Organization
- Serbia
- INIS RN
- 38033190
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; EVALUATION; HEAT TRANSFER; MATHEMATICAL MODELS; SAFETY ANALYSIS; SAFETY STANDARDS; THERMAL HYDRAULICS
- Descriptors DEC
- ENERGY TRANSFER; FLUID MECHANICS; HYDRAULICS; MECHANICS; STANDARDS
Optional Information
- Notes
- 4 refs.. 1 tabs.