MNSR transient analysis using the RELAP5/Mod3.2 code

Dawah ,  a S. ,  Khattab K. 외 1명

Nuclear Engineering and Technology

2020 .09

Neutronic assessment of BDBA scenario at the end of Isfahan MNSR core life

M. Ahmadi ,  A. Pi ,  ouzmand 외 1명

Nuclear Engineering and Technology

2018 .01

Facility to study neutronic properties of a hybrid thorium reactor with a source of thermonuclear neutrons based on a magnetic trap

And ,  ey V. A ,  zhannikov 외 12명

Nuclear Engineering and Technology

2020 .11

Application of a new neutronics/thermal-hydraulics coupled code for steady state analysis of light water reactors

Safavi Ami ,  Esteki Mohammad Hossein ,  Mi 외 3명

Nuclear Engineering and Technology

2020 .08

Study on Nuclear Test Scheme and Test Results for Safety Neutron Measurement System in Research Reactor

Bae ,  Sanghoon ,  Kim 외 3명

한국방사성폐기물학회 학술대회

2017 .01

Time-frequency analysis of reactor neutron noise under bubble disturbance and control rod vibration

Baoxin Yuan ,  Simao Guo ,  Wankui Yang 외 4명

Nuclear Engineering and Technology

2021 .04

Neutron activation analysis: Modelling studies to improve the neutron flux of Americiume-Beryllium source

Abdessamad Didi ,  Ahmed Dadouch ,  Otman Jaï 외 3명

Nuclear Engineering and Technology

2017 .06

Adaptive energy group division in the few-group cross-section generation for full spectrum reactor modeling with deterministic method

Yang Yichen ,  Zheng Youqi ,  Du Xianan 외 1명

Nuclear Engineering and Technology

2024 .06

A Proposal on Evaluation Method of Neutron Absorption Performance to Substitute Conventional Neutron Attenuation Test

Kim ,  Jae Hyun ,  Kim 외 17명

방사선방어학회지

2016 .01

Neutron irradiation impact on structural and electrical properties of polycrystalline Al2O3

Kuma ,  Sunil ,  Shah Sejal 외 5명

Nuclear Engineering and Technology

2024 .02

MAINTAINING THE CLOSE-TO-CRITICAL STATE OF THORIUM FUEL CORE OF HYBRID REACTOR OPERATED UNDER CONTROL BY D-T FUSION NEUTRON FLUX

Se ,  gey V. Bedenko ,  And 외 15명

Nuclear Engineering and Technology

2021 .06

Calibration of digital wide-range neutron power measurement channel for open-pool type research reactor

주성문 ,  이종복 ,  서상문

Nuclear Engineering and Technology

2018 .01

Neutronics analysis of the ion cyclotron resonance heating antenna of the China Fusion Engineering Test Reactor

Wang Gaoxiang ,  Qin Chengming ,  Zheng Shanliang 외 3명

Nuclear Engineering and Technology

2024 .08

Numerical analysis of the effect of pitch of discrete arc-shaped baffles on thermohydraulic performance of solar air heaters

Gia Huy Ngo ,  Raj Kuma ,  Daeho Lee

대한기계학회 춘추학술대회

2024 .11

Target-Moderator-Refl ector system for 10 – 30 MeV proton accelerator-driven compact thermal neutron source: Conceptual design and neutronic characterization

전병일 ,  김종율 ,  이은중 외 3명

Nuclear Engineering and Technology

2020 .01

연구용 원자로의 건전성 평가를 위한 수치해석적 중성자 조사 재료변형 예측기법 개발

박준근 ,  석태현 ,  허남수

한국압력기기공학회 논문집

2024 .06

A high-stability neutron generator for industrial online elemental analysis

Chen Xiang-quan ,  Xiong Lei ,  Xie Hui 외 3명

Nuclear Engineering and Technology

2024 .04

Sensitivity Analysis of Core Neutronic Parameters in Electron Accelerator-driven Subcritical Advanced Liquid Metal Reactor

Ma ,  ziye Eb ,  ahimkhani

Nuclear Engineering and Technology

2016 .01

Characterization of a Neutron Beam Following Reconfi guration of the Neutron Radiography Reactor (NRAD) Core and Addition of New Fuel Elements

Aa ,  on E. C ,  aft

Nuclear Engineering and Technology

2016 .01

Shielding design and analyses of the cold neutron guide hall for the KIPT neutron source facility

Zhaopeng Zhong ,  Yous ,  y Goha

Nuclear Engineering and Technology

2018 .01