Preparing Emergency Medicine Residents for the Certifying Exam: A Pilot Study of a Longitudinal Simulation-Based Assessment Program. [PDF]
AEM Educ TrainABSTRACT Background The American Board of Emergency Medicine (ABEM) has recently introduced a new Certifying Exam, which incorporates assessment of performance in a simulated clinical environment. Simulation‐based assessments allow for reproducible, controlled evaluations.
Yee J +13 more
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He jishu, 2023 BackgroundSilicon carbide (SiC) composite claddings are candidate solutions for accident resistant fuel claddings in light water reactors.PurposeThis study aims to estimate the failure probability of a double-layer structured SiC cladding under a loss-of-
CAO Liwen, YI Boquan, HAO Zulong
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RELAP5 Modeling of a Siphon Break Effect on the Brazilian Multipurpose Reactor
Brazilian Journal of Radiation Sciences, 2021 This work presents the thermal-hydraulic simulation of the Brazilian Multipurpose Reactor (RMB) using the RELAP5/Mod3 code. The RMB will provide Brazil with a fundamental infrastructure for the national development on activities of the nuclear sector in ...
Humberto Vitor Soares +2 more
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Analysis for fuel rod performance under LOCA based on the FROBA-ROD 2.0 code
International Journal of Advanced Nuclear Reactor Design and Technology, 2021 Loss of Coolant Accident (LOCA) is one of the major design-basis accidents in LWRs. Fuel rod may fail due to the rupture of the cladding. By developing a LOCA simulation module, the steady-state fuel rod performance analysis code, FROBA-ROD, is now ...
Haoyu Liao +7 more
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Overcoming the uncertainty in a research reactor LOCA in level-1 PSA; Fuzzy based fault-tree/event-tree analysis [PDF]
Journal of Optimization in Industrial Engineering, 2020 Probabilistic safety assessment (PSA) which plays a crucial role in risk evaluation is a quantitative approach intended to demonstrate how a nuclear reactor meets the safety margins as part of the licensing process.
Masoud Mohsendokht +1 more
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Deriving formula to simulate the radiological behavior during LOCA in open pool type reactor
Brazilian Journal of Radiation Sciences, 2022 This study aims to model the radiological consequences that result from loss of coolant accident in open pool research reactor of 22 MW power. The loss of coolant accident results from rupture in the cooling systems of the reactor and consequently ...
Amr Abdelhady
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Degradation of Cr-coated cladding under the simulated Loss-of-Coolant Accident phenomena
Acta Polytechnica CTU Proceedings, 2022 The present study focuses on the evaluation of the mechanical properties degradation of Cr-coated Zr-alloy fuel cladding. The main objective of the work is to find a suitable methodology to evaluate the mechanical properties degradation of coated ...
Petr Červenka +6 more
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Development of a super-high rang γ monitor for high temperature and pressure environment
He jishu, 2021 BackgroundUnder accident conditions of nuclear power plants, radiation measurement is needed in the high temperature, high humidity and high pressure environment in the containment vessel where the ordinary radiation monitor does not work normally ...
SUN Guangzhi +8 more
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EXPERIMENTAL STUDY OF DAMAGED CR-COATED FUEL CLADDING IN POST-ACCIDENT CONDITIONS
Acta Polytechnica CTU Proceedings, 2020 To enhance the safety of nuclear power, the focus of researchers all around the world has recently mainly objected on the development of Accident Tolerant Fuels.
Petr Červenka +6 more
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The VINON-LOCA test facility: exploring the LOCA phenomenology through an out-of-pile thermal sequence on irradiated pressurized fuel rod [PDF]
EPJ Web of Conferences, 2021 Since the out-of-pile semi-integral tests performed at Studsvik in 2011 for the NRC [1] and the Halden Loss-Of-Coolant Accident (LOCA) test series IFA-650 [2], a major safety interest has raised for Fuel Fragmentation, Relocation and Dispersal (FFRD ...
Biard B. +12 more
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