Published 1984
| Version v1
Miscellaneous
Open
One dimensional reactor core model
Creators
- 1. Institut Jozef Stefan, Ljubljana (Yugoslavia)
Description
The one dimensional model of neutron dynamic in reactor core was developed. The core was divided in several axial nodes. The one group neutron diffusion equation for each node is solved. Feedback affects of fuel and water temperatures is calculated. The influence of xenon, boron and control rods is included in cross section calculations for each node. The system of equations is solved implicitly. The model is used in basic principle Training Simulator of NPP Krsko. (author)
Availability note (English)
Available from INIS in electronic form; Also available from the Institute of Nuclear Sciences VINCAFiles
38033181.pdf
Files
(201.1 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:59807dd5497931d472894246f89e5d6e
|
201.1 kB | Preview Download |
Additional details
Additional titles
- Original title (Serbian)
- Jednodimenzionalni model reaktorskog jezgra
Publishing Information
- Publisher
- Society for Electronics,Telecommunications, Automation, and Nuclear Engineering
- Imprint Place
- Belgrade (Yugoslavia)
- Imprint Pagination
- 8 p.
- Report number
- INIS-RS--0733
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
- 38033181
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BORON; CONTROL ROD WORTHS; CROSS SECTIONS; KRSKO REACTOR; NEUTRON DIFFUSION EQUATION; ONE-GROUP THEORY; REACTOR CORES; REACTOR KINETICS; REACTOR SIMULATORS; TEMPERATURE COEFFICIENT; XENON OSCILLATIONS
- Descriptors DEC
- ANALOG SYSTEMS; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ELEMENTS; ENRICHED URANIUM REACTORS; EQUATIONS; FUNCTIONAL MODELS; KINETICS; NEUTRON TRANSPORT THEORY; PARTIAL DIFFERENTIAL EQUATIONS; POISONING; POWER REACTORS; PWR TYPE REACTORS; REACTIVITY COEFFICIENTS; REACTOR COMPONENTS; REACTORS; SEMIMETALS; SIMULATORS; THERMAL REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs., 1 figs.