Neutronic and thermohydraulic blanket analysis for hybrid fusion–fission reactor during operation; Nuclear Engineering and Technology; Vol. 55, iss. 7
| Parent link: | Nuclear Engineering and Technology.— .— Amsterdam: Elsevier Science Publishing Company Inc. Vol. 55, iss. 7.— 2023.— P. 2678-2686 |
|---|---|
| Awduron Eraill: | Bedenko S. V. Sergey Vladimirovich, Lutsik I. O. Igor Olegovich, Prikhodko V. V. Vadim Vadimovich, Matyushin A. A. Anton Andreevich, Polozkov S. D. Sergey Dmitrievich, Shmakov V, M. Vladimir Mikhaylovich, Modestov D. G. Dmitry Gennadjevich, Vega-Carrillo H. R. Hector Rene |
| Crynodeb: | Title screen This work demonstrates the results of full-scale numerical experiments of a hybrid thorium-containing fuel plant operating in a state close to critical due to a controlled source of D–T neutrons. The proposed facility represented a level of generated power (∼10–100 MWt) in a small pilot. In this work, the simulation of the D–T neutron plasma source operation in conjunction with the facility blanket was performed. The fission of fuel nuclei and the formation of spatial-energy release were studied in this simulation, in pulsed and stationary modes of the facility operation. The optimization results of neutronic and fluid dynamics studies to level the emerging offsets of the radial energy formed in the volume of the facility multiplying part due to the pulsed operation of the D–T neutron plasma source were presented. The results will be useful in improving the power control-based subcriticality monitoring method in coupled systems of the “pulsed neutron source–subcritical fuel assembly” type Текстовый файл AM_Agreement |
| Iaith: | Saesneg |
| Cyhoeddwyd: |
2023
|
| Pynciau: | |
| Mynediad Ar-lein: | https://doi.org/10.1016/j.net.2023.03.032 |
| Fformat: | Electronig Pennod Llyfr |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=680196 |
Eitemau Tebyg
Maintaining the close-to-critical state of thorium fuel core of hybrid reactor operated under control by D-T fusion neutron flux; Nuclear Engineering and Technology; Vol. 53, iss. 6
Cyhoeddwyd: (2021)
Cyhoeddwyd: (2021)
Facility to study neutronic properties of a hybrid thorium reactor with a source of thermonuclear neutrons based on a magnetic trap; Nuclear Engineering and Technology; Vol. 52, iss. 11
Cyhoeddwyd: (2020)
Cyhoeddwyd: (2020)
A complementary study on the thermophysical and gas-dynamic characteristics of a hybrid fusion-fission reactor facility during operation; Nuclear Engineering and Design; Vol. 399
Cyhoeddwyd: (2022)
Cyhoeddwyd: (2022)
Fusion-fission hybrid reactor with a plasma source of deuterium-tritium neutrons in a linear configuration; Progress in Nuclear Energy; Vol. 154
Cyhoeddwyd: (2022)
Cyhoeddwyd: (2022)
Power density dynamics in a nuclear reactor with an extended in-core pulse-periodic neutron source based on a magnetic trap; Nuclear Energy and Technology; Vol. 6, № 3
Cyhoeddwyd: (2020)
Cyhoeddwyd: (2020)
Fuel Evolution in Hybrid Reactor Based on Thorium Subcritical Assembly with Open Trap as Fusion Neutron Source (Computer Simulations); Plasma and Fusion Research: JSPF; Vol. 14
Cyhoeddwyd: (2019)
Cyhoeddwyd: (2019)
Use of Thorium in Thermal-Neutron Reactors: Computation Model and Comparison of Neutronic Codes; Journal of Industrial Pollution Control; Vol. 32, iss. 2
Cyhoeddwyd: (2016)
Cyhoeddwyd: (2016)
Influence of the transition from symmetric to asymmetric fission mode on the average total kinetic energy and neutron multiplicity; Physical Review C; Vol. 108 - Iss. 1
Cyhoeddwyd: (2023)
Cyhoeddwyd: (2023)
Use of Thorium in Thermal-Neutron Reactors: Different Types of Fuel Compositions in VVER-1000 Reactor Cell; Journal of Industrial Pollution Control; Vol. 32, iss. 2
Cyhoeddwyd: (2016)
Cyhoeddwyd: (2016)
A technique for conducting of reactor in-situ tests of optical fibres and FBG-sensors intended for in-vessel applications in thermonuclear facilities; Fusion Engineering and Design; Vol. 191
Cyhoeddwyd: (2023)
Cyhoeddwyd: (2023)
Experiments on tritium generation and yield from lithium ceramics during neutron irradiation; International Journal of Hydrogen Energy; Vol. 46, iss. 13
Cyhoeddwyd: (2021)
Cyhoeddwyd: (2021)
Conceptual Design of Experimental Facility for Large-Diameter NTD-Si at the IRT-T Reactor; Atom Indonesia; Vol. 47, iss. 1
Cyhoeddwyd: (2021)
Cyhoeddwyd: (2021)
Gas-cooled thorium reactor at various fuel loadings and its modification by a plasma source of extra neutrons; Nuclear Science and Techniques; Vol. 30, iss. 12
Cyhoeddwyd: (2019)
Cyhoeddwyd: (2019)
Computational neutron emission spectrometry and radiation assessment in VVER-1200 reactor nuclear fuel; Radiation Physics and Chemistry; Vol. 229
Cyhoeddwyd: (2025)
Cyhoeddwyd: (2025)
A fuel for generation IV nuclear energy system: Isotopic composition and radiation characteristics; Applied Radiation and Isotopes; Vol. 147
Cyhoeddwyd: (2019)
Cyhoeddwyd: (2019)
Peculiarities of the radiation formation in dispersed microencapsulated nuclear fuel; Nuclear Energy and Technology; Vol. 5, № 1
Cyhoeddwyd: (2019)
Cyhoeddwyd: (2019)
Neutronic Properties Optimization Of The Irt-T Reactor Core; Journal of Industrial Pollution Control; Vol. 32, iss. 2
Cyhoeddwyd: (2016)
Cyhoeddwyd: (2016)
Modeling of a device for conducting experiments under low reactor neutron fluence rate conditions; Nuclear Energy and Technology; Vol. 11, iss. 2
Cyhoeddwyd: (2025)
Cyhoeddwyd: (2025)
ANN-driven unfolding of epithermal neutron spectra in variable-geometry beam-shaping assemblies; Radiation Physics and Chemistry; Vol. 232
Cyhoeddwyd: (2025)
Cyhoeddwyd: (2025)
Analytical estimation of the central reflector impact on thermal and fast neutron flux density in research reactors; 11th International Forum on Strategic Technology (IFOST 2016); Pt. 2
Cyhoeddwyd: (2016)
Cyhoeddwyd: (2016)
On computation of fission neutron age in metal-water mixtures; Bulletin of the Tomsk Polytechnic University; Vol. 311, № 4 : Power engineering
gan: Alekseev A. V.
Cyhoeddwyd: (2007)
gan: Alekseev A. V.
Cyhoeddwyd: (2007)
Parameters of the neutron field at the Prizm-AN stand in the neutronic measurement laboratory; Applied Radiation and Isotopes; Vol. 219
Cyhoeddwyd: (2025)
Cyhoeddwyd: (2025)
To the nature of dark matter; Russian Physics Journal; Vol. 66, No. 7
gan: Dudkin G. N. Gennadiy Nikolaevich
Cyhoeddwyd: (2023)
gan: Dudkin G. N. Gennadiy Nikolaevich
Cyhoeddwyd: (2023)
Estimation of the neutron yield generated by neutron source based on pulsed power proton accelerator in 7Li(p, n)7Be reaction; Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment; Vol. 1075
Cyhoeddwyd: (2025)
Cyhoeddwyd: (2025)
A study of the characteristics of a pulsed accelerator-driven neutron source based on lithium targets; Radiation Physics and Chemistry; Vol. 244
Cyhoeddwyd: (2026)
Cyhoeddwyd: (2026)
Влияние отравления бериллиевых блоков на нейтронно-физические характеристики реактора ИВГ.1М; Известия Томского политехнического университета [Известия ТПУ]; Т. 326, № 2
gan: Прозорова И. В. Ирина Валентиновна
Cyhoeddwyd: (2015)
gan: Прозорова И. В. Ирина Валентиновна
Cyhoeddwyd: (2015)
Investigation of pulse shape neutron-gamma discrimination; Resource-Efficient Technologies; No 3
gan: Avetisyan R. V.
Cyhoeddwyd: (2019)
gan: Avetisyan R. V.
Cyhoeddwyd: (2019)
Effect of changing the neutron moderator in a thermal subcritical nuclear reactor; Applied Radiation and Isotopes; Vol. 188
Cyhoeddwyd: (2022)
Cyhoeddwyd: (2022)
Evaluating the dependency of neutron spectra and absorbed dose rates on the collimation field size in fast neutron therapy; Heliyon; Vol. 7, iss. 11
gan: Shehada A. Abdullah
Cyhoeddwyd: (2021)
gan: Shehada A. Abdullah
Cyhoeddwyd: (2021)
The problems of utilizing graphite of stopped graphite-uranium reactors; Bulletin of the Tomsk Polytechnic University; Vol. 310, № 2
Cyhoeddwyd: (2007)
Cyhoeddwyd: (2007)
Aluminum coating performance enhancement: novel coating and characterization techniques; Перспективы развития фундаментальных наук; Т. 1 : Физика
gan: Salman A. M.
Cyhoeddwyd: (2024)
gan: Salman A. M.
Cyhoeddwyd: (2024)
Nuclear Doping of Single-Crystal Silicon in the IRT-T Pool Type Research Nuclear Reactor; Actual Problems of Electronic Instrument Engineering (APEIE-2018); Vol. 1, pt. 1
Cyhoeddwyd: (2018)
Cyhoeddwyd: (2018)
Feasibility study of using IRT-T research reactor for BNCT applications; Applied Radiation and Isotopes; Vol. 166
Cyhoeddwyd: (2020)
Cyhoeddwyd: (2020)
Особенности нагрева немагнитных изделий прямоугольного сечения во вращающемся поле постоянных магнитов; Известия Томского политехнического университета [Известия ТПУ]; Т. 325, № 3 : Химия и химические технологии
Cyhoeddwyd: (2014)
Cyhoeddwyd: (2014)
Neutron pumping of active medium formed by gadolinium isotopes Gd155 and Gd156 pair; Applied Radiation and Isotopes; Vol. 171
Cyhoeddwyd: (2021)
Cyhoeddwyd: (2021)
Investigation of hydrogen isotopes interaction with lithium CPS under reactor irradiation; Fusion Engineering and Design; Vol. 124
Cyhoeddwyd: (2017)
Cyhoeddwyd: (2017)
Influence of the fast neutron irradiation on the IR-LEDs reliability; ISROS 2014
Cyhoeddwyd: (2014)
Cyhoeddwyd: (2014)
Conceptual design for a new heterogeneous 241Am-9Be neutron source assembly using SOURCES4C-MCNPX hybrid simulations; Applied Radiation and Isotopes; Vol. 153
gan: Ghal-Eh N. Nima
Cyhoeddwyd: (2019)
gan: Ghal-Eh N. Nima
Cyhoeddwyd: (2019)
Neutron Spectrum Measured by Activation Diagnostics in Deuterium Gas-Puff Experiments on the 3 MA GIT-12 Z-Pinch; IEEE Transactions on Plasma Science; Vol. 45, iss. 12
Cyhoeddwyd: (2017)
Cyhoeddwyd: (2017)
The dependency of fast neutron flux and spectra on the collimation-field size and geometry for fast neutron therapy purposes; Radiation Effects and Defects in Solids; Vol. 176, iss. 9-10
gan: Shehada A. Abdullah
Cyhoeddwyd: (2021)
gan: Shehada A. Abdullah
Cyhoeddwyd: (2021)
Eitemau Tebyg
-
Maintaining the close-to-critical state of thorium fuel core of hybrid reactor operated under control by D-T fusion neutron flux; Nuclear Engineering and Technology; Vol. 53, iss. 6
Cyhoeddwyd: (2021) -
Facility to study neutronic properties of a hybrid thorium reactor with a source of thermonuclear neutrons based on a magnetic trap; Nuclear Engineering and Technology; Vol. 52, iss. 11
Cyhoeddwyd: (2020) -
A complementary study on the thermophysical and gas-dynamic characteristics of a hybrid fusion-fission reactor facility during operation; Nuclear Engineering and Design; Vol. 399
Cyhoeddwyd: (2022) -
Fusion-fission hybrid reactor with a plasma source of deuterium-tritium neutrons in a linear configuration; Progress in Nuclear Energy; Vol. 154
Cyhoeddwyd: (2022) -
Power density dynamics in a nuclear reactor with an extended in-core pulse-periodic neutron source based on a magnetic trap; Nuclear Energy and Technology; Vol. 6, № 3
Cyhoeddwyd: (2020)