NEUTRONIC AND THERMAL HYDRAULICS ANALYSIS OF CONTROL ROD EFFECT ON THE OPERATION SAFETY OF TRIGA 2000 REACTOR [PDF]
Urania, 2019 NEUTRONIC AND THERMAL HYDRAULICS ANALYSIS OF CONTROL ROD EFFECT ON THE OPERATION SAFETY OF TRIGA 2000 REACTOR. Analysis of neutronic and thermal-hydraulics parameters of whole operation cycle is very important for the safety of reactor operation.
Surian Pinem +2 more
doaj +2 more sources
Neutronic assessment of BDBA scenario at the end of Isfahan MNSR core life
Nuclear Engineering and Technology, 2018 The present study aims to assess the excess induced reactivity in a Miniature Neutron Source Reactor (MNSR) for a Beyond Design Basis Accident (BDBA) scenario.
M. Ahmadi, A. Pirouzmand, A. Rabiee
doaj +2 more sources
Nuclear data libraries for IFMIF-DONES neutronic calculations [PDF]
, 2022 International Fusion Materials Irradiation Facility-DEMO Oriented NEutron Source (IFMIF-DONES) is an installation aimed to irradiate with a high neutron flux materials relevant for the construction of the DEMOnstration fusion power plant (DEMO), in order
Mota, F. +6 more
core +6 more sources
A basic evaluated neutronic data file for elemental scandium [PDF]
, 1992 This report documents an evaluated neutronic data file for elemental scandium, presented in the ENDF/B-VI format. This file should provide basic nuclear data essential for neutronic calculations involving elemental scandium.
Smith, A. B. +2 more
core +3 more sources
Analysis of fuel rejuvenation times in a fusion breeder reactor fuelled with a mixture of uranium-thorium oxides for the CANDU reactor [PDF]
Nuclear Technology and Radiation Protection, 2017 This study presents the determination of fuel rejuvenation times in a D-T fusion breeder reactor fuelled with a mixture of natUO2 and ThO2 for multi-reuse of nuclear fuels in CANDU-37 reactors.
Bakir Gizem, Yapici Huseyin
doaj +1 more source
ON-THE-FLY INTERPOLATION OF CONTINUOUS TEMPERATURE-DEPENDENT THERMAL NEUTRON SCATTERING DATA IN RMC CODE [PDF]
EPJ Web of Conferences, 2021 Thermal neutron scattering data have an important influence on the high-fidelity neutronics calculation of thermal reactors. Due to the limited storage capabilities of computers, a discrete ACE representation of the secondary neutron energy and angular ...
Zheng Lei, Feng Zhiyuan, Wang Kan
doaj +1 more source
Numerical techniques for coupled neutronic/thermal hydraulic nuclear reactor calculations [PDF]
The solution of coupled neutronic/thermal hydraulic nuclear reactor calculations requires the treatment of the nonlinear feedback induced by the thermal hydraulic dependence of the neutron cross sections.
Betts, Curt M.
core +5 more sources
On calculation of the neutron charge radius [PDF]
Nuclear Physics A, 2002 4 Pages, Contribution to the Third International Conference on Perspectives in Hadronic Physics, Trieste, Italy, 7-11 May ...
openaire +2 more sources
Evaluation of neutronic performance for the VVER-1000 reactor core with regenerated uranium-plutonium fuel [PDF]
Nuclear Energy and Technology, 2023 The possibility has been considered for the VVER-1000 reactor fuel loading to be formed based on regenerated fuel with the use of the spent fuel accumulated in reactors of the same type.
Viktor V. Semishin
doaj +3 more sources
Science and Technology of Nuclear Installations, 2011 Monte Carlo neutron transport codes are usually used to perform criticality calculations and to solve shielding problems due to their capability to model complex systems without major approximations.
Diego Ferraro, Eduardo Villarino
doaj +1 more source