Results 11 to 20 of about 63,160 (263)

Analysis of Calculation Model for Primary Coolant Fission Products

open access: yesEnergy Engineering and Control Systems, 2023
The sources of radioactive contamination of the primary coolant by fission products when the unit is operating at the rated power are as follows: defect fuel elements with gas leakiness and substantial damages, surface contamination of the outer surfaces
Stepan Lys
doaj   +1 more source

TO THE PROBLEM OF COOLING OF THE LIQUID AND SOLID COMPONENTS, FORMED AT THERMAL AUTOPSY OF THE FUEL ELEMENTS ON THE SURFASE OF THE VIBROTRANSPORTER

open access: yesИзвестия высших учебных заведений: Проблемы энергетики, 2017
Results of experimental investigation of heat-exchange liquid and solid components introduced (in the model materials), formed at thermal opening of the fuel elements on the inclined surface of the vibrotransporter.
B. G. Sapozhnikov   +3 more
doaj   +1 more source

Shielding Design and Dose Evaluation for HTR-PM Fuel Transport Pipelines by QAD-CGA Program

open access: yesScience and Technology of Nuclear Installations, 2021
The spherical fuel elements are adopted in the high-temperature gas-cooled reactor pebble-module (HTR-PM). The fuel elements will be discharged continuously from the reactor core and transported into the fuel transport pipelines during the reactor ...
Sheng Fang   +6 more
doaj   +1 more source

Study on Performance of Coated Particle Dispersed Fuel Pellet Prepared by Spark Plasma Sintering

open access: yesYuanzineng kexue jishu, 2023
Accident tolerant fuel can improve the safety of nuclear reactor core and strengthen the ability of nuclear reactor to withstand serious accidents. Coated particle dispersed fuel has become a hot research topic in accident tolerant fuel in recent years ...
LIU Wei;SHAO Zongyi;LIU Wentao;MENG Ying;FENG Shuaishuai;CAI Zhenfang
doaj  

Establishment and verification of chemical interaction model between fast reactor fuel and cladding under high burnup

open access: yesHe jishu, 2022
BackgroundUranium dioxide fuel elements of fast neutron reactor operate under the conditions of high burnup, high neutron fluence rate, high line power and high temperature.
CHEN Qidong, GAO Fuhai
doaj   +1 more source

Feasibility Study on the Initial Kartini Reactor Core Using Plate Type Fuel Elements

open access: yesScience and Technology of Nuclear Installations, 2022
The plate type fuel element conversion is proposed to solve a supply problem of TRIGA standard rod type fresh fuel in the long term and to extend the lifetime by reducing the dependence of buying imported elements.
Argo Satrio Wicaksono   +2 more
doaj   +1 more source

Technological aspects of energy optimization during operating vehicles and increase their environmental safety [PDF]

open access: yesMATEC Web of Conferences, 2019
The paper discusses an actual scientific and practical problem of expanding the fuel base of the transport means by using biodiesel fuel in the form of ethyl esters made of rapeseed, sunflower and soybean oils. The choice of the optimal blend composition
Karnaukh Mykola   +2 more
doaj   +1 more source

Preparation process and performance of graphene oxide-doped UO2 pellets

open access: yesHe jishu
BackgroundUranium dioxide (UO2) has been broadly employed as nuclear fuel in nuclear reactors. However, the poor thermal conductivity of UO2 compromises the safety of the reactor owing to possible sharp temperature gradients.
WEN Feng   +6 more
doaj   +1 more source

Mathematical and Computer Modeling of Convective Heat Transfer in Fuel Cartridges of Fuel Elements with Different Shapes and Packing of Rods

open access: yesJournal of Mechanical Engineering, 2022
The paper consists of three sections and is of an informational and generalizing nature, indicating promising areas for further research. The first section "R-functions method in mathematical modeling of convective heat transfer in fuel cartridges with ...
Kyrylo V. Maksymenko-Sheiko   +3 more
doaj   +1 more source

Study on Preparation Process and Performance of Tungsten-based Uranium Nitride Microspheres Dispersed Fuel

open access: yesYuanzineng kexue jishu
CERMET dispersion fuel is currently a hotspot in the research and development of fuels for nuclear thermal propulsion (NTP) reactors. Uranium nitride (UN) has a uranium density 40% greater than that of uranium dioxide (UO2), as well as the advantages of ...
LIU Wentao1, 2,  DU Jiangping1, 2,  ZHAO Yumeng1, 2,  MA Chunyu2,  LIU Wei1, 2,  CAI Zhenfang2
doaj   +1 more source

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