On the spectrum of moderated neutrons emitted by the isotropic source in the gas fuel by V. O. Tarasov, S. A. Chernezhenko, A. O. Kakaev, O. D. Berezovskiy, V. V. Voytenko

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Engineering Design of a Voloxidizer with a Double Reactor for the Hull Separation of Spent Nuclear Fuel Rods by Young-Hwan Kim, Yung-Zun Cho, Jae-Won Lee, Ju-Hoo Lee, Sang-Chae Jeon, Do-Hee Ahn

“…A voloxidizer with a double reactor capable of processing several tens of kilograms of HM/batch of nuclear spent fuel has been developed for the decladding and voloxidation of rod-cuts into hulls and pellets through the conversion of UO2 pellets to U3O8 powder. …”
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Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl3 Molten Salt by Sang-Kwon Lee, Sung-Wook Kim, Jun-Hyuk Jang, Min Ku Jeon, Eun-Young Choi

“…The results suggest that the LKU salt technique can be used to separate REs and, potentially, TRUs from actual spent nuclear fuels (SNFs). It is thought that this technique is advantageous over the conventional TRU recovery techniques because the majority of the SNFs (i.e., UO2) remained stable, thus reducing the process burden. …”
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Preliminary Study on the Fabrication of Particulate Fuel through Pressureless Sintering Process by Jong-Hwan Kim, Jung-Won Lee, Ki-Hwan Kim, Chan-Bock Lee

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Modelling key reactive processes relevant to bisulfide transport through highly compacted bentonite by Md Abdullah Asad, Tarek L. Rashwan, Ian L. Molnar, Mehran Behazin, Peter G. Keech, Magdalena M. Krol

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Process and Validation of Depletion Database Based on Evaluated Nuclear Data Libraries by LUO Hao, LI Jie, HUANG Shanfang, WANG Kan

“…Analysis of nuclear reactor fuel composition and irradiation characteristics plays a crucial role in reactor design, licensing, safety analysis, and decommissioning. …”
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NUMERICAL SIMULATIONS OF SPENT NUCLEAR FUEL STORAGE CASE THERMAL STATE FOR A DRY CHAMBER-TYPE STORAGE by O. K. Bezyukov, P. M. Afanasyev

“…In today's world, nuclear power is highly dependent on the closing components of the nuclear fuel cycle and, in particular, on the long-term storage of spent nuclear fuel (SNF) and the possibility of its processing.…”
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Dataset of observables for small modular lead-cooled fast reactor MOX spent nuclear fuelMendeley Data by Victor J. Casas-Molina, Pablo Romojaro, Gwennaelle Nourry, Gert Van den Eynde, Luca Fiorito, Ivan Merino-Rodríguez, Tom Dhaene, Ivo Couckuyt

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Method for assessment of residual heat generation within preparation of spent nuclear fuel shipment from research reactors by S. H. Kadalev

“…In the presented paper is considered the approach to an assessment of the residual heat generation within preparation of spent nuclear fuel (SNF) shipment from research reactors. …”
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Molecular Dynamics Simulation of Thermal and Irradiation Creep Behavior of FeCrAl Alloy for Nuclear Fuel Cladding by Bei CAO, Wenxiu BAI, Huan YAO, Junmei WU, Chunyu YIN, Ping CHEN

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Nuclear Power Plants: Recent Advances Towards to Safety by Lorenzo De Micheli, Claudia Giovedi, Alfredo Abe, Almir Oliveira Neto

“… The Fukushima Daiichi accident in 2011 significantly impacted the licensing process for nuclear power plants (NPPs) due to the necessity to mitigate the hydrogen generation from the reaction between water/steam and zirconium-based alloy cladding material. …”
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COATED CLADDING BEHAVIOR DURING HIGH-TEMPERATURE TRANSIENTS by Adéla Chalupová, Jakub Krejčí, Ladislav Cvrček, Martin Ševeček, Vojtěch Rozkošný, Antonín Přibyl, Patricie Halodová, Petra Gávelová

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Research progress and development trends in the anti-oxidation mechanism and performance enhancement of uranium nitride as an accident-resistant nuclear fuel by Yu ZHANG, Xuwen ZHAO, Yujuan ZHANG, Yu YANG, Wenti LÜ, Xiaoguang LIU, Mingfu CHU, Zhenliang YANG, Jingkun XU, Changchun GE

“…Given the low oxidation resistance of uranium nitride-based nuclear fuel under in-pile service conditions, this paper first discusses the oxidation process and mechanism of UN. …”
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Stability of Glass-ceramic Solidified Body of High Level Chloride Salts from Pyro-reprocessing of Spent Nuclear Fuels by CHANG Jiong, WANG Jiateng, LIU Xiao, LI Longfei, BAO Liangjin, LONG Haoqi, TAN Shengheng

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Analysis of the Processes in Spent Fuel Pools in Case of Loss of Heat Removal due to Water Leakage by Algirdas Kaliatka, Viktor Ognerubov, Virginijus Vileiniškis, Eugenijus Ušpuras

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Improved damage tolerance of SiC-based nuclear fuel cladding with novel multi-layered SiC coating design at 1200 °C by Guanjie Yuan, David H. Cook, Harold Barnard, Edward Lahoda, Peng Xu, Robert O. Ritchie, Dong Liu

“…These results provide new insights into the failure mechanisms of multi-layer SiC coatings and offer guidance for the future design of accident-tolerant nuclear fuel claddings.…”
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CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR. PART 10 - PRESENTATION OF THE DECOMMISSIONING... by Constantin D. STANESCU, Gabi ROSCA FARTAT, Constantin POPESCU

“…This paper presents a solution proposed by the authors in order to achieve of a cutting and extracting device operating panel for the decommissioning of the horizontal fuel channels in the CANDU 6 nuclear reactor. The Cutting and Extraction Device (CED) is fully automated, connected by wires to a Programmable Logic Controller (PLC) and controlled from a Human Machine Interface (HMI). …”
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EXPERIMENTAL STUDY OF LOCAL HYDRODYNAMICS AND MASS EXCHANGE PROCESSES OF COOLANT IN FUEL ASSEMBLIES OF PRESSURIZED WATER REACTORS by S. M. Dmitriev, A. A. Barinov, A. N. Pronin, V. D. Sorokin, A. E. Khrobostov

“…The results of experimental studies of local hydrodynamics and mass exchange of coolant flow behind spacer and mixing grids of different structural versions that were developed for fuel assemblies of domestic and foreign nuclear reactors are presented in the article. …”
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DETAILS OF OPERATIONS PERFORMED BY THE REMOTE CONTROL ROBOT (CONCEPT) TO THE HORIZONTAL FUEL CHANNEL DURING DECOMMISSIONING PHASE OF NUCLEAR REACTOR CALANDRIA STRUCTURE. PART I: OU... by Constantin POPESCU, Gabi ROȘCA-FÂRTAT, Nicolae PANĂ

“…The authors contribution to this paper is to present a concept solution of a remote control robot (RCR) used for the horizontal fuel channels pressure tube decommissioning in the CANDU nuclear reactor. …”
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DETAILS OF OPERATIONS PERFORMED BY THE REMOTE CONTROL ROBOT (CONCEPT) TO THE HORIZONTAL FUEL CHANNEL DURING DECOMMISSIONING PHASE OF NUCLEAR REACTOR CALANDRIA STRUCTURE. PART II: I... by Constantin POPESCU, Gabi ROȘCA-FÂRTAT, Nicolae PANĂ

“…The authors contribution to this paper is to present a concept solution of a remote control robot (RCR) used for decommissioning of the horizontal fuel channels pressure tube in the CANDU nuclear reactor. …”
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