Published 1983
| Version v1
Miscellaneous
BETL-B code for calculation of the fuel element cladding temperature during accidents
Creators
Description
A mathematic model and a code for calculation of the fuel element cladding temperature during accidents with coolant leakage are described. The computation results are given for different basic assumptions about the film boiling on the fuel element surface
Additional details
Additional titles
- Original title (Russian)
- Бетл-Б- вычислительная программа для определения температуры оболочек тепловыделяющих элементов при аварийных радиационных инцидентах
Publishing Information
- Imprint Title
- Radiation safety of Nuclear Power Plants operation. Book 2
- Journal Page Range
- p. 158-169.
- Report number
- INIS-mf--10580(v.2)
Conference
- Title
- Radiation safety of Nuclear Power Plants operation.
- Dates
- May 1982.
- Place
- Vil'nyus (USSR).
INIS
- Country of Publication
- International Centre for Scientific and Technical Information (ICSTI)
- Country of Input or Organization
- International Centre for Scientific and Technical Information (ICSTI)
- INIS RN
- 18023937
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; COMPUTERIZED SIMULATION; FAILURE MODE ANALYSIS; FUEL CANS; GERMAN DEMOCRATIC REPUBLIC; NUCLEAR POWER PLANTS; REACTOR ACCIDENTS; TEMPERATURE DISTRIBUTION; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; DEVELOPED COUNTRIES; ENRICHED URANIUM REACTORS; EUROPE; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SIMULATION; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs.; 6 figs.; 1 tab. Imprint:Obespechenie radiatsionnoj bezopasnosti pri ehkspluatatsii AEhS.;Sbornik dokladov nauchno-tekhnicheskoj konferentsii SEhV, g. Vil'nyus, maj 1982 g. Kniga 2.