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- [7] Neutron Flux Interpolation with Finite Element Method in the Nuclear Fuel Cell Calculation using Collision Probability Method 4TH ASIAN PHYSICS SYMPOSIUM: AN INTERNATIONAL EVENT, 2010, 1325 : 253 - 256
- [8] Neutron Distribution in the Nuclear Fuel Cell using Collision Probability Method with Quadratic Flux Approach 1ST ANNUAL APPLIED SCIENCE AND ENGINEERING CONFERENCE (AASEC), IN CONJUCTION WITH THE INTERNATIONAL CONFERENCE ON SPORT SCIENCE, HEALTH, AND PHYSICAL EDUCATION (ICSSHPE), 2017, 180
- [9] THE EFFECT OF A MODERATOR IN THE CENTRAL REGION OF A HOLLOW FUEL-ELEMENT AS A FUNCTION OF THE NEUTRON-SPECTRUM COMPOSITION ATOMKERNENERGIE-KERNTECHNIK, 1981, 39 (04): : 237 - 239
- [10] DEVELOPMENT OF THE SURFACE PSEUDO-SOURCE METHOD FOR CALCULATING NEUTRON FIELDS IN CELLS WITH A BUNDLE OF FUEL-ELEMENT RODS SOVIET ATOMIC ENERGY, 1979, 46 (03): : 172 - 177