22 research outputs found
Analysis constants for database of neutron nuclear data
At present there is a variety of experimental and calculation nuclear data which arerather entirely presented in the following evaluated nuclear data libraries: ENDF (USA), JEFF(Europe), JENDL (Japan), TENDL (Russian Federation), ROSFOND (Russian Federation).Libraries of nuclear data, used for neutron-physics calculations in programs: Scale (OrigenArp),MCNP, WIMS, MCU, and others. Nevertheless all existing nuclear data bases, includingevaluated ones, contain practically no information about threshold neutron reactions on {232}Thnuclei; available values of outputs and cross-sections significantly differ by orders. The workshows necessity of nuclear constants corrections which are used in the calculations of grids andthorium storage systems. The results of numerical experiments lattices and storage systemswith thorium
A variable-geometry beam-shaping assembly for accelerator-based BNCT
Although the beam shaping assemblies (BSAs) for reactor-based Boron Neutron Capture Therapy (BNCT) facilities are typically of a single design, the accelerator beams with the possibility to provide neutron spectrum to give characteristics which are optimum for different treatment sites and tumor depth generally may require a fine-tuning procedure which can be undertaken with variable-geometry BSA. In this study, a special geometry is proposed for use with a hybrid photoneutron source equipped with drill-chuck type head. Both the neutron spectrum and epithermal neutron flux can be treated by changing the BSA geometry
Development of thorium-containing nuclear fuel cycle
The results providing advantages of thorium-232 as a reproducing nuclide in comparison with uranium-238 as a part of nuclear fuel of new generation reactors are presented. The explanation of the effects which were found earlier in numerical simulation of parameters of open thorium - plutonium nuclear fuel cycle is offered. Scientific and technical solutions allow considering the possibility of including thorium-232 in the fuel of nuclear reactors, which are based on existing design solutions, and beginning the design of new generation materials: a new generation of fuel rods and fuel assemblies, where the isotope uranium-238 will be completely replaced with thorium-232
ΠΠ»ΠΈΡΠ½ΠΈΠ΅ ΡΠ°ΡΠΏΡΠ΅Π΄Π΅Π»Π΅Π½ΠΈΡ Π³Π°Π΄ΠΎΠ»ΠΈΠ½ΠΈΠΉ ΡΠΎΠ΄Π΅ΡΠΆΠ°ΡΠΈΡ ΡΠ²ΡΠ»ΠΎΠ² ΡΠ΅Π°ΠΊΡΠΎΡΠ° ΠΠΠΠ -1000 Π½Π° Π²ΡΠ³ΠΎΡΠ°Π½ΠΈΠ΅
Π Π°Π·Π»ΠΈΡΠ½ΡΠΉ ΡΠΎΡΡΠ°Π² ΠΈ ΠΏΡΠΎΡΡΡΠ°Π½ΡΡΠ²Π΅Π½Π½ΠΎΠ΅ ΡΠ°ΡΠΏΡΠ΅Π΄Π΅Π»Π΅Π½ΠΈΠ΅ Π²ΡΠ³ΠΎΡΠ°ΡΡΠΈΡ
ΠΏΠΎΠ³Π»ΠΎΡΠΈΡΠ΅Π»Π΅ΠΉ ΠΏΠΎ-ΡΠ°Π·Π½ΠΎΠΌΡ Π²Π»ΠΈΡΡΡ Π½Π° ΡΠ°Π·ΠΌΠ½ΠΎΠΆΠ°ΡΡΠΈΠ΅ ΠΈ ΡΠ΅ΠΏΠ»ΠΎΡΠΈΠ·ΠΈΡΠ΅ΡΠΊΠΈΠ΅ ΡΠ²ΠΎΠΉΡΡΠ²Π° ΡΠ΅Π°ΠΊΡΠΎΡΠ°. Π ΡΠ°Π±ΠΎΡΠ΅ ΡΠΎΠ·Π΄Π°Π½Π° ΡΠ°ΡΡΠ΅ΡΠ½Π°Ρ 3D ΠΌΠΎΠ΄Π΅Π»Ρ Π’ΠΠ‘ ΡΠ΅Π°ΠΊΡΠΎΡΠ° Ρ Π²ΡΠ³ΠΎΡΠ°ΡΡΠΈΠΌΠΈ ΠΏΠΎΠ³Π»ΠΎΡΠΈΡΠ΅Π»ΡΠΌΠΈ. Π ΠΊΠ°ΡΠ΅ΡΡΠ²Π΅ Π²ΡΠ³ΠΎΡΠ°ΡΡΠΈΡ
ΠΏΠΎΠ³Π»ΠΎΡΠΈΡΠ΅Π»Π΅ΠΉ ΠΈΡΠΏΠΎΠ»ΡΠ·ΡΡΡΡΡ ΡΡΠ°Π΄ΠΈΡΠΈΠΎΠ½Π½ΠΎ-ΠΏΡΠΈΠΌΠ΅Π½ΡΠ΅ΠΌΡΠ΅ Gd2O3-ΡΠΎΠ΄Π΅ΡΠΆΠ°ΡΠΈΠ΅ ΡΠ²ΡΠ»Ρ ΠΈ ΡΠ²ΡΠ»Ρ Ρ AmO2. ΠΡΠΎΠ²Π΅Π΄Π΅Π½Π½ΡΠ΅ ΡΠ°ΡΡΠ΅ΡΡ ΠΏΠΎΠ·Π²ΠΎΠ»ΠΈΠ»ΠΈ ΠΈΡΡΠ»Π΅Π΄ΠΎΠ²Π°ΡΡ Π½Π΅ΠΉΡΡΠΎΠ½Π½ΠΎ-ΡΠΈΠ·ΠΈΡΠ΅ΡΠΊΠΈΠ΅ ΡΠ²ΠΎΠΉΡΡΠ²Π° ΡΠ΅Π°ΠΊΡΠΎΡΠ° ΠΈ Π½ΠΈΠ²Π΅Π»ΠΈΡΠΎΠ²Π°ΡΡ, Π²ΠΎΠ·Π½ΠΈΠΊΠ°ΡΡΠΈΠ΅ ΠΎΡΡΠ΅ΡΡ ΡΠ½Π΅ΡΠ³ΠΎΠ²ΡΠ΄Π΅Π»Π΅Π½ΠΈΡ Π² ΠΏΠ΅ΡΠ΅Ρ
ΠΎΠ΄Π½ΡΡ
ΡΠ΅ΠΆΠΈΠΌΠ°Ρ
ΡΠΊΡΠΏΠ»ΡΠ°ΡΠ°ΡΠΈΠΈ
Features of the formation of radiation in a new-generation of fuel with a complex internal heterogeneous structure
Particularities of spatial kinetics of hybrid thorium reactor installation containing the long neutron source based on magnetic trap
In this work, we study the features of the spatial kinetics of installation as a hybrid thorium reactor with an elongated plasma neutron source based on a magnetic trap. The active zone of the installation under study consists of an assembly of hexagonal fuel blocks of a unified design and a long solenoid with a high-temperature plasma column passing through the axial region of the core. Combining engineering expertise in creating nuclear reactors with a physics-technical potential for obtaining high-temperature plasma in a long magnetic trap we ensure the solution of the multidisciplinary problem posed. These studies are of undoubted practical interest, since they are necessary to substantiate the safety of operation of such hybrid systems. The research results will allow optimizing the active zone of the hybrid system with leveling the resulting offset radial and axial energy release distributions. Results of our study will be the basis for the development of new and improvement of existing methods of criticality control in related systems such as "pulsed neutron source - subcritical fuel assembly"