Using software based on the Monte-Carlo method for receiving the few-group homogenized macroscopic interaction cross-section
The constant preparation issues are important for performing the few-group analysis for different states of the reactor core. Besides, the constant preparation method influences the further calculations accuracy and quality. The transport software products (deterministic codes) are usually used for...
Main Author: | Galchenko V. V. Abdulaev А. М. Shlapak І. І. |
---|---|
Format: | Article |
Language: | English |
Published: |
Odessa National Polytechnic University
2017-12-01
|
Series: | Trudy Odesskogo Politehničeskogo Universiteta |
Subjects: | |
Online Access: | http://pratsi.opu.ua/articles/show/11996 |
Similar Items
-
Using of the Serpent code based on the Monte-Carlo method for calculation of the VVER-1000 fuel assembly characteristics
by: V. V. Galchenko, et al.
Published: (2016-12-01) -
Calculation of radiation fields in the VVER-1000 concrete biological shield using Monte Carlo code Serpent
by: O. M. Khotiaintseva, et al.
Published: (2023-09-01) -
VVER-1000 reactor model using the Serpent 2 code for core power distribution calculation
by: V. V. Ilkovych
Published: (2023-12-01) -
VVER-1000 BENCHMARK INTERPRETATION WITH MONTE CARLO CODE MCS
by: Setiawan Fathurrahman, et al.
Published: (2021-01-01) -
Estimation of the systematic error constituents in the calculations of the critical systems by the Monte Carlo method
by: V. V. Galchenko, et al.
Published: (2009-09-01)