Published 1992
| Version v1
Miscellaneous
Open
Temperature distribution calculations in TRIGA fuel element after the pulse
Description
The computer program TEMPUL for calculating radial temperature distribution in a fuel element after the pulse operation is shortly described. It is based on one-dimensional diffusion equation for heat transfer in cylindrical geometry and implicit boundary condition at the element-coolant interface, defined by empirical boiling curve, which relates the heat flux from the rod and the difference between the fuel element surface temperature and water boiling point. As an example the results of such analysis of maximal allowed pulse at TRIGA Mark II reactor in Ljubljana are presented. (author)
Abstract (Slovenian)
V delu je kratko predstavljen program TEMPUL za racunanje radialne porazdelitve temperature v gorivnem elementu po pulzu. Osnova programa je difuzijska enacba za prevajanje toplote v cilindricni geometriji z implicitno podanim robnim pogojem na zunanji meji gorivnega elementa, ki je dolocen z empiricno podano vrelno krivuljo, ki povezuje toplotni tok iz gorivne palice in razliko med temperaturo na povrsini gorivnega elementa in temperaturo vrelisca vode pri danem tlaku. Kot primer uporabe programa TEMPUL so predstavljeni rezultati analize najvecjega dovoljenega pulza v reaktorju TRIGA Mark II v Ljubljani. (author)Files
38056702.pdf
Files
(300.7 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:ee53a94f01a435e33b5235cfb47e8c5c
|
300.7 kB | Preview Download |
Additional details
Publishing Information
- Publisher
- Nuclear Society of Slovenia
- Imprint Place
- Ljubljana (Slovenia)
- ISBN
- 961-90004-0-4
- Imprint Title
- First Meeting of the Nuclear Society of Slovenia, Proceedings
- Imprint Pagination
- 332 p.
- Journal Page Range
- p. 3-10
- Report number
- INIS-SI--07-001
Conference
- Title
- First Meeting of the Nuclear Society of Slovenia
- Dates
- 11-12 Jun 1992
- Place
- Bovec (Slovenia)
INIS
- Country of Publication
- Slovenia
- Country of Input or Organization
- Slovenia
- INIS RN
- 38056702
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DIFFUSION EQUATIONS; FUEL ELEMENTS; PULSES; T CODES; TEMPERATURE DISTRIBUTION; TRIGA-2-LJUBLJANA REACTOR
- Descriptors DEC
- COMPUTER CODES; DIFFERENTIAL EQUATIONS; ENRICHED URANIUM REACTORS; EQUATIONS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; PARTIAL DIFFERENTIAL EQUATIONS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; TRIGA TYPE REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs., 4 figs. Imprint:332 refs., 50 tabs., 133 figs.