A5074675517- Nuclear reactor physics and engineering
- Graphite, nuclear technology, radiation studies
- Nuclear Materials and Properties
- Nuclear Physics and Applications
- Nuclear and radioactivity studies
- Nuclear Engineering Thermal-Hydraulics
- Risk and Safety Analysis
- Molten salt chemistry and electrochemical processes
- Radiation Therapy and Dosimetry
- Advanced Power Generation Technologies
- Combustion and Detonation Processes
- Engineering Diagnostics and Reliability
- Crystallization and Solubility Studies
- Nuclear Issues and Defense
- Bauxite Residue and Utilization
- Coal Combustion and Slurry Processing
- Radiation Dose and Imaging
- Environmental and Industrial Safety
- Fusion materials and technologies
- Fire effects on concrete materials
- Radiative Heat Transfer Studies
- Metallurgical Processes and Thermodynamics
- Radioactivity and Radon Measurements
- Iron and Steelmaking Processes
National Nuclear Center of the Republic of Kazakhstan
1998-2024
Institute of Atomic Energy
2018-2023
This paper is devoted to the creation of an information and analytical system (IAS) which under development manage data obtained in experiments investigations justify safety atomic energy, National Nuclear Center Republic Kazakhstan (RSE NNC RK) has been conducting for over 30 years. The main components IAS determining its consumer capabilities unit that will allow programs planned view technical requirements them based on results previous experiments, generalized consolidated by processing...
Облучение экспериментальных животных активированной нейтронами радиоактивной пылью: разработка и реализация методапервые результаты международного многоцентрового исследования
Abstract The paper provides calculation of various campaign scenarios the IVG.1M Research Reactor with LEU-fuel. schemes replacement and transfer fuel are suggested. Several options considered that include a complete partial spent nuclear fresh one, change in reactor reactivity margin during is calculated.
The article presents the results of computational studies to substantiate possibility testing fuel Multipurpose hYbrid Research Reactor for a High-tech Applications reactor (MYRRHA) in Impulse Graphite research (IGR). A scheme conducting experiments is proposed, which allows simulating operating conditions MYRRHA elements wide range changes their thermohydraulic parameters, including accidents with destruction pellets, blocking flow area and stopping coolant flow. method calculations has...
A large volume of scientific and research activities is currently carried out in substantiation new projects on nuclear reactor safety, which high emphasis placed “beyond-design basis” accidents, spite the fact that applied technical solutions reduce probability such accidents occurrence. To study parameters severe develop measures to mitigate consequences an experimental base necessary, enables emergency situation modelling maximally close real conditions. The National Nuclear Center (NNC)...
Abstract During a severe accident in sodium-cooled fast reactors, molten core materials could be discharged from the region toward lower sodium of reactor vessel through coolant channels, such as control rod guide tubes. Typical SFRs have plenum with limited depth and volume, inlet located under region. Therefore, it is important to evaluate coolability into depth- volume-limited plenum. In present study, deepen understanding on plenum, conditions which form solidified fragments were...
Research of prototype fuel elements and assemblies in in-pile tests are an integral part substantiating the safety operability installations being designed, also necessary for validating calculation codes. Despite long service life a large number studies conducted IGR reactor, capabilities this reactor under conditions implementing long-term experiments at minimum power still not fully clear. This paper presents substantiation possibility experiment with during implementation operation mode...
IVG.1M research reactor performs tests of WCTCs-LEU in order to determine whether channels correspond technical requirements or not and obtain experimental data necessary take a decision concerning manufacture batch standard their insertion into core based on results researches. The paper presents comparative assessment technological parameters (flow rate, pressure, temperature) during in-pile testing U 235 burn-out calculation according implemented start-ups reactor.
Possibilities of experimental study the model fuel assembly (FA) destruction ASTRID reactor in a severe accident were studied this paper. Experiments with FA can be carried out research impulse graphite (IGR) [1] framework joint program between RSE NNC RK and CEA, called SAIGA (SAIGA – Severe Accident InPile experiments for Generation IV Astrid project) [2]. core consists an inner zone heterogeneous height, which principle separation high enrichment into two zones (upper lower) is applied by...
The article presents the results of studies to justify project for decommissioning IGR reactor facility. Based on a comprehensive engineering and radiation survey, system boundaries be decommissioned were determined, compliance facility (IGR RF) state, its systems equipment with design requirements, executive operational documentation was established. neutronic calculations fission products’ activity activation products, as well exposure dose rate ionizing at different distances from main...
The RSE NNC RK branch “Institute of Atomic Energy” has been conducted investigations in the field nuclear power safety since late 1982. These have recently resulted accumulation a vast amount experimental data widely applied creation, verification and validation calculation codes intended to analyze behavior reactors under transient emergency modes including analysis reactor conditions course propagation severe accident with fuel melting. However, positive effect application these...
The characteristics of the effective dose field and rate ionizing radiation formed in room IGR reactor during its operation at a constant power 100 MW for 40 seconds have been estimated. value experimental device has determined order to assess level potential load on small-sized neutron detectors (fission chambers), which are supposed be used measure local values fast flux density irradiation reactor. To carry out calculations, models with an upper ceiling, concrete biological protection two...