Publications & Works

Articles 20
All (20)
SCI-E, SSCI, AHCI (20)
SCI-E, SSCI, AHCI, ESCI (20)
Scopus (20)
Papers Presented at Peer-Reviewed Scientific Conferences 9

1. A pencil beam kernel model for flattening filter-free X-ray beams

5th International Conference on Radiation and Applications in Various Fields of Research, RAD 2017, Budva, mne, 12 - 16 June 2017, vol.2, pp.186-190, (Full Text) Creative Commons License identifier

2. Investigation of Turbulence Characteristics of the Flow in a 1x3 Fuel Rod Bundle with Spacer Grids Using Computational Fluid Dynamics Method

26th International Conference Nuclear Energy for New Europe (NENE), Bled, Slovenia, 11 - 14 September 2017, (Full Text) identifier

3. Investigation of Thermal Turbulent Flow Characteristics of Wire wrapped Fuel Pin Bundle of Sodium Cooled Fast Reactor in Lattice-Boltzmann Framework

25th International Conference Nuclear Energy for New Europe (NENE), Portoroz, Slovenia, 5 - 08 September 2016, (Full Text) identifier

4. The Effect of Tube Arrangement and Turbulence Models for Steady Flow Past Tube Bundles

25th International Conference Nuclear Energy for New Europe (NENE), Portoroz, Slovenia, 5 - 08 September 2016, (Full Text) identifier

5. Simplified Pencil Beam Kernel For Unfiltered Energies

57th Annual Meeting and Exhibition of the American-Association-of-Physicists-in-Medicine (AAPM), California, United States Of America, 12 - 16 July 2015, vol.42, pp.3497, (Summary Text) identifier

6. Turbulent Flow Simulations Of Wire-wrapped Fuel Pin Bundle Of Sodium Cooled Fast Reactor In Lattice-Boltzmann Framework

24th International Conference on Nuclear Energy for New Europe (NENE), Portoroz, Slovenia, 14 - 17 September 2015, (Full Text) identifier

7. Analysis of LOFA in BWR Spent Fuel Storage Pool

24th International Conference on Nuclear Energy for New Europe (NENE), Portoroz, Slovenia, 14 - 17 September 2015, (Full Text) identifier

9. A CFD model of two-phase flow in BWRS: Results of application to BFBT benchmark exercise 2

12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12, Pittsburgh, PA, United States Of America, 30 September - 04 October 2007, (Full Text) identifier
Metrics

Publication

32

Publication (WoS)

26

Publication (Scopus)

22

Citation (WoS)

161

H-Index (WoS)

8

Citation (Scopus)

156

H-Index (Scopus)

8

Project

11

Thesis Advisory

14

Open Access

1
UN Sustainable Development Goals