Carbon 14 distribution during spent fuel dissolution - Application to an UOx3 spent fuel
, 2015 Carbon 14 ($^{14}$C) is a radionuclide formed during the irradiation of nuclear fuel, primarily from nitrogen 14, impurity present in the fuel, and from oxygen 17 present in oxide matrix. One of the objectives related to this radionuclide concerns the knowledge of its distribution in the different flows during the spent fuel dissolution, some of which ...
Crozet, M., Ferlay, G.
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Study on combustible gas generation and radionuclide release during underwater handling of the AM reactor spent fuel [PDF]
Nuclear Energy and Technology, 2021 Introduction. The paper addresses studies on the accumulation of combustible gases during underwater handling simulations for the leaky spent nuclear fuel from the AM reactor.
Artyom Z. Gayazov +4 more
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Radiological characteristics of spent nuclear fuel from small modular reactors under consideration for deployment in Ukraine [PDF]
Nuclear Technology and Radiation Protection, 2023 Small modular reactors represent a promising technology for power generation, offering solutions to the energy crisis and mitigating greenhouse gas emissions.
Khotiaintseva Olena +2 more
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Lessons learned from a review of international approaches to spent fuel management
EPJ Nuclear Sciences & Technologies, 2016 Worldwide, a variety of approaches to the management of spent fuel have been adopted. A review of approaches adopted internationally was undertaken to inform decision making on spent fuel management in UK.
Hambley David +5 more
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Reactor criticals and spent fuel systems similarities
Acta Polytechnica CTU Proceedings, 2022 Many conservative assumptions for subcriticality assessment calculations have to be made in current calculations of spent fuel storage systems. This is due to a fact that there is no available database of benchmarks containing spent fuel or materials ...
Matěj Šikl
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Safety Concerning Transportation of Spent Fuel [PDF]
Journal of Nuclear Science and Technology, 1989 The Central Research Institute of Electric Power Industry (CRIEPI) has been conducting, under contract with the Science and Technology Agency of Japan, the spent fuel transport cask reliability dem...
NAGAKURA, Tadashi +5 more
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HEAT EXCHANGE CONDITIONS IN THE DRY STORAGE CONTAINER FOR SPENT NUCLEAR FUEL OF POWER REACTORS
Elektrotehnìka ta Elektroenergetika, 2018 Purpose. The safety substantiation of the spent nuclear fuel of power reactors WWER-1000 of Zaporizhska NPP dry storage facility operation by carrying out of numerical study of the thermal processes inside dry storage container. Methodology. Mathematical
S.V. Alyokhina
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Automotive Fuel Processor Development and Demonstration with Fuel Cell Systems [PDF]
, 2005 The potential for fuel cell systems to improve energy efficiency and reduce emissions over conventional power systems has generated significant interest in fuel cell technologies.
Cells, Nuvera Fuel
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A smart HVAC retrofit system to improve fire safety in mission-critical facilities
Case Studies in Thermal EngineeringThis study presents a simulation-based evaluation of an integrated HVAC and smoke control retrofit aimed at improving fire resilience and occupant tenability in simulated nuclear power plant Main Control Rooms (MCRs).
Beomgyu Kim
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Deployment evaluation methodology for the electrometallurgical treatment of DOE-EM spent nuclear fuel [PDF]
, 1998 Part of the Department of Energy (DOE) spent nuclear fuel (SNF) inventory may require some type of treatment to meet acceptance criteria at various disposition sites.
Adams, J.P., Ramer, R.J., Dahl, C.A.
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