Test calculations by new version of C-PORCA
Creators
- 1. Nuclear Power Plant, Paks (Hungary)
- 2. TS ENERCON, Budapest (Hungary)
Description
During next years new kinds of fuel assemblies will be introduced at the NPP Paks. Regular usage of these fuel assemblies indicates a few questions about applicability and accuracy diffusion model applied to core analysis during in-core fuel management and core surveillance. A more accurate and reliable calculation is needed of the pinwise power and indicate the need of its more reliable validation. To achieve the aimed requirements two main developments have been carried out in the C-PORCA code. To validate the accuracy of the thermal model the Helios code was used again. The fulfilled modifications in the C-PORCA code, focused on the enhancement of the accuracy of the code in the vicinity of the control assemblies especially next to the connection area between the follower and the absorber parts. (author)
Additional details
Publishing Information
- Publisher
- Magyar Tudomanyos Akademia, KFKI Atomenergia Kutato Intezet
- Imprint Place
- Budapest (Hungary)
- ISBN
- 963-372-616-6
- Imprint Title
- Proceedings of the ninth Symposium of AER
- Imprint Pagination
- 802 p.
- Journal Page Range
- p. 53-64
Conference
- Title
- 9. Symposium of AER
- Dates
- 4-8 Oct 1999
- Place
- Demaenovska Dolina (Slovakia)
INIS
- Country of Publication
- Hungary
- Country of Input or Organization
- Hungary
- INIS RN
- 31063823
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; COMPUTER CALCULATIONS; FUEL ASSEMBLIES; H CODES; P CODES; REACTOR KINETICS; WWER-3 REACTOR
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; KINETICS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- 7 refs.