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ANDREA 2: Improved Version of Code for Reactor Core Analysis
In recent years, the core physics code ANDREA has been significantly improved for ANDREA. The new version of the code has gone through extensive validation both on the benchmarks and experimental data. The modular ...
JF - Jaderná energetika
- 2014 •
- D
Rok uplatnění
D - Stať ve sborníku
ANDREA Recalculation of Operation History of VVER - 440
Macrocode ANDREA has been developed in UJV Rez a.s. It is used for neutronic calculation of fuel batches. During its development, the code was verified and validated for reactors VVER-1000 and new version ANDREA 2.0 was val...
JF - Jaderná energetika
- 2014 •
- D •
- Link
Rok uplatnění
D - Stať ve sborníku
Výsledek na webu
ANDREA: Advanced nodal diffusion code for reactor analysis
Article included in conference proceedings, containing description of the status of development of SW application ANDREA...
BG - Jaderná, atomová a molekulová fyzika, urychlovače
- 2005 •
- D
Rok uplatnění
D - Stať ve sborníku
Program ANDREA-REF for reference core calculations
Program for reference reference core calculations, created by close coupling of lattice code HELIOS for cross section preparation on the level of single fuel assemblies and of code ANDREA for 3D core calculations in diffusi...
BG - Jaderná, atomová a molekulová fyzika, urychlovače
- 2013 •
- R •
- Link
Rok uplatnění
R - Software
Výsledek na webu
ANDREA recalculation of operation history of VVER-440
Macrocode ANDREA has been developed in UJV Rez a.s. It is used for neutronic calculation of fuel batches. During its development, the code was verified and validated for reactors VVER-1000 and new version ANDREA 2.0 was val...
JF - Jaderná energetika
- 2014 •
- D •
- Link
Rok uplatnění
D - Stať ve sborníku
Výsledek na webu
ANDREA-SP3
ANDREA-SP3 is a code for core calculations of light water reactors with hexagonal assemblies, where the solver is based on nodal method with SP3 approximation of transport equation....
BG - Jaderná, atomová a molekulová fyzika, urychlovače
- 2010 •
- R
Rok uplatnění
R - Software
Validated and certified neutron, thermohydraulic and thermomechanical codes for verifying the safety characteristics of fuel charges
by the ANDREA code is described, which will be carried out in subsequent follow-up steps. power reactor (VVER-440) developed in the programs "Advanced Nodal Diffusion code for REactor Analysis" (ANDREA) and the Pu...
Nuclear related engineering; (nuclear physics to be 1.3);
- 2023 •
- O
Rok uplatnění
O - Ostatní výsledky
The influence of temperature model uncertainty for ANDREA calculations.
The review evaluate influence of temperature uncertainty for neutronic calculations. For fuel assemblies with three different plutonium content were prepared correct temperature models. The results were compared with calculations with temperature mod...
JF - Jaderná energetika
- 2010 •
- O
Rok uplatnění
O - Ostatní výsledky
Using the ANDREA macrocode for calculations with TRISO fuel
As part of the work on the Energy Well reactor project, the possibility of using the ANDREA/HELIOS tool combination for operational calculations of the proposed reactor was tested and shortcomings of the developed computational models to pre...
Nuclear related engineering; (nuclear physics to be 1.3);
- 2022 •
- O
Rok uplatnění
O - Ostatní výsledky
ANDREA 2.2 and 2.3-Advances in modelling of VVER cores
In 2016 a new version of code ANDREA for core design and reload safety analysis of VVER reactors has been released. The new code version includes several major calculations (without temperature feedback) into the code
Nuclear related engineering; (nuclear physics to be 1.3);
- 2017 •
- Jimp •
- Link
Rok uplatnění
Jimp - Článek v periodiku v databázi Web of Science
Výsledek na webu
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