Comparative evaluation of the steady state fuel rod thermal behaviour code GAPCON-THERMAL-2 and the integral fuel rod performance code URANUS
Creators
- 1. Technische Hochschule Darmstadt (Germany, F.R.). Inst. fuer Reaktortechnik
Description
A comparison between the steady state fuel rod thermal behaviour code GAPCON-THERMAL-2 and the integral fuel rod performance code URANUS was made by analyzing with both codes a few sample data cases representing idealized LWR fuel conditions. The results reveal certain discrepancies in the thermal submodels of the codes, but quite consistent fuel maximum temperature predictions are achieved. Capabilities of the GAPCON-THERMAL-2 for mechanical performance analyses appear very limited, but as far as the calculation of thermal behaviour is concerned the mechanical parts of the code seem to be quite acceptable. The URANUS results for mechanical phenomena seem very plausible. Yet, no reference to experimental findings was made at this stage of the evaluation. The running times of URANUS appear very short, especially if demands for detail are optimized. After refining certain submodels and sufficient verification against experimental data URANUS is potentially a most valuable tool for a wide variety of practical LWR fuel applications. (author)
Availability note (English)
MF available from INIS under the Report Number.
Files
Additional details
Additional titles
- Augmented title (English)
- LWR
Publishing Information
- ISBN
- 951-38-0619-7
- Imprint Pagination
- 32 p.
- Report number
- VTT-YDI--34
INIS
- Country of Publication
- Finland
- Country of Input or Organization
- Finland
- INIS RN
- 9405112
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- BWR TYPE REACTORS; COMPARATIVE EVALUATIONS; COMPUTER CODES; CREEP; FUEL RODS; G CODES; HEAT TRANSFER; HIGH TEMPERATURE; PERFORMANCE; PWR TYPE REACTORS; SPATIAL DISTRIBUTION; STEADY-STATE CONDITIONS; STRESSES; U CODES; VERY HIGH TEMPERATURE
- Descriptors DEC
- DISTRIBUTION; ENERGY TRANSFER; FUEL ELEMENTS; MECHANICAL PROPERTIES; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS