Results 1 to 10 of about 2,910 (211)
Nuclear data uncertainty on generation IV fast reactors criticality calculations analysis comparison [PDF]
Nuclear Energy and Technology, 2023 The new calculation code capabilities are applied in the current work as well as important fast reactor criticality parameters uncertainty assessment articles’ results based on different nuclear data libraries and covariance matrices.
Dimitar G. Chereshkov +3 more
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EPJ Nuclear Sciences & Technologies, 2023 Five Euratom projects launched since 2017 in support of the development of ESNII/Generation-IV reactor systems are briefly presented in the paper in terms of key objectives, results, and recommendations for the future.
Mikityuk Konstantin +4 more
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Conceptual issues of the cold filter trap development for the sodium coolant purification in fast-neutron reactors [PDF]
Nuclear Energy and Technology, 2020 The paper presents the results of studying the peculiarities of heat and mass exchange in cold traps for the sodium purification of impurities in fast reactor circuits both in dedicated test areas simulating various trap components (isothermal sump ...
Viktor V. Alekseev +2 more
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Nuclear Engineering and Technology, 2019 This paper presents the drop performance test of the control rod assembly which is one of the main components strongly related to the safety of the prototype generation IV sodium-cooled fast reactor.
Jin Gwan Son +4 more
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Nuclear Engineering and Technology, 2020 As the refueling of a sodium-cooled fast reactor is conducted by rotating part of the reactor head without opening it, the monitoring of existing obstacles that can disturb the rotation of the reactor head is one of the most important issues.
Hoe-Woong Kim +3 more
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COUPLED MODELLING OF THE EBR-II SHRT-45R INCLUDING PHOTON HEAT DEPOSITION [PDF]
EPJ Web of Conferences, 2021 The Fast REactor NEutronics/Thermal-hydraulICs (FRENETIC) code has been developed during the last years at Politecnico di Torino, implementing a full-core coupled neutronic/thermal-hydraulics model for steady-state and transient analysis of liquid-metal ...
Valerio Domenico +4 more
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FAST REACTOR MULTIPHYSICS AND UNCERTAINTY PROPAGATION WITHIN WIMS [PDF]
EPJ Web of Conferences, 2021 For liquid metal-cooled fast reactors (LMFRs), improved predictive modelling is desirable to facilitate reactor licensing and operation and move towards a best estimate plus uncertainty (BEPU) approach.
Lindley Ben +9 more
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Thorium application in the medium-sized sodium-cooled fast reactor [PDF]
E3S Web of Conferences, 2019 The report presents an analysis of the medium-sized Sodium-Cooled Fast Reactor (SFR) core with Thorium-based Mixed-Oxide fuel. The introduction of Transuranics (TRU) to the fuel was to allow long-lived nuclear waste incineration.
Raaj Saasthaa Arumuga Kumar Eeshu +3 more
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Stability characteristics of the 500 mw Indian PFBR [PDF]
Nuclear Technology and Radiation Protection, 2015 After the successful operation of the fast breeder test reactor for over two decades, India is now nearing the completion of a 500 MW (electrical) prototype fast breeder reactor. This commercial scale power reactor is a sodium-cooled, pool-type,
Anuraj Vijayan L. +2 more
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Nuclear Engineering and Technology, 2022 A hypothetical core destructive accident (HCDA) has received widespread attention as one of the most serious accidents in sodium-cooled fast reactors. This study combined recent advantages in numerical methods to realize realistic modeling of the complex
Zhihong Guo, Xiaodong Chen, Guoqing Hu
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