Verification of safety rod calculations by experiments on the RB reactor
Verifikacija raspolozivih racunarskih programa za proracun efekta sigurnosnih sipki eksperimentima na reaktoru RB
АуториPetrović, Ivan M.
МетаподациПриказ свих података о документу
Safety rod calculations performed by computation codes for global reactor core analysis were verified on experimental results obtained by measurements on RB reactor Three-dimensional code TRITON and two-dimensional codes VAMPIR and KONEL were applied In the first two codes finite difference method is used for the space discretization of the diffusion equation and in the third finite element method Calculation errors were analyzed for X-Y-Z, X-Y and R-Z geometries The obtained results are on the frame of the expected calculational errors (author)
Извор:31st Conference - ETAN '87: Society for Electronics, Telecommunications, Automation, and Nuclear Engineering, 1987, IX.57-IX.64
- Society for Electronics,Telecommunications, Automation, and Nuclear Engineering
- 31. Conference - ETAN'87: Society for Electronics, Telecommunications, Automation, and Nuclear Engineering; ETAN'87: 31. Konferencija za elektroniku, telekomunikacije, automatiku i nuklearnu tehniku; Bled (Yugoslavia); 1-5 Jun 1987.