Published 1995
| Version v1
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Fuel rod performance analysis of the Kozloduy NPP WWER reactors at core reloads with the PIN-micro code
Creators
- Stefanova, S.
- Passage, G.
- Simeonova, V.
- Radev, R.
- Manolova, M.
- Haralampieva, Z.
- Antov, A.
- Styanova, I.
- Simeonov, T.
- Spasova, V.
- Peychinov, Z.
- Hadjieva, M.
- Kotev, G.
- Bylgarska Akademiya na Naukite, Sofia (Bulgaria). Inst. za Yadrena Izsledvaniya i Yadrena Energetika
- Kombinat Atomna Energetika, Kozloduj (Bulgaria)
Description
The necessity of the process of modeling the fuel behaviour at core reloading and accompanying uncertainties is substantiated. The results from numerical analysis of thermomechanical processes in fuel rods of WWER-440 (with expended core life) and WWER-1000 (with highest burnup) in the Kozloduy NPP units are reported. The quasi-two-dimensional PIN-micro code based on the G-TH-2, for steady state and slow transients, has been used. The operational margins defined are: Maximal fuel temperature <1000oC-1100oC, fission gas release <1-3%, gas pressure <80 bar, which is in the prediction capabilities of the PIN-micro code. The report is in a poster form. 14 figs., 1 tab. 15
Availability note (English)
MF available from INIS under the Report Number.Files
27045264.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 17 p.
- Report number
- INIS-mf--14770
Conference
- Title
- Specialists' meeting on WWER fuel- and thermal-hydraulic behaviour.
- Dates
- 7-10 Nov 1995.
- Place
- Sofia (Bulgaria).
INIS
- Country of Publication
- Bulgaria
- Country of Input or Organization
- Bulgaria
- INIS RN
- 27045264
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPILED DATA; FISSION PRODUCT RELEASE; FUEL RODS; HIGH PRESSURE; P CODES; REACTOR FUELING; SAFETY ANALYSIS; STEADY-STATE CONDITIONS; TEMPERATURE RANGE 1000-4000 K; WWER-3 REACTOR; WWER-5 REACTOR
- Descriptors DEC
- COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; INFORMATION; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; TEMPERATURE RANGE; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS