Journal of Nuclear Science and Technology

Papers
(The H4-Index of Journal of Nuclear Science and Technology is 11. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2021-04-01 to 2025-04-01.)
ArticleCitations
Criticality evaluation considering nonuniformity effect using Monte Carlo perturbation method199
Numerical simulation of bubble hydrodynamics for pool scrubbing111
Fuel cycle features of RFBB fast reactor with advanced fuel27
Early-phase core degradation interpretation by interaction between fuel cladding and fuel components in Fukushima Daiichi nuclear power plant Unit 224
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (II): 58 Fe(n,γ) 59 Fe22
Research on soft errors induced by alpha particles and atmospheric neutrons based on 28 nm field programmable gate array21
Bayesian statistical model for cladding high-temperature burst under loss-of-coolant accident conditions15
Effects of azimuthal temperature distribution and rod internal gas energy on ballooning deformation and rupture opening formation of a 17 × 17 type PWR fuel cladding tube under LOCA-simulated burst co13
Improvements in the particle and heavy-ion transport code system (PHITS) for simulating neutron-response functions and detection efficiencies of a liquid organic scintillator12
An estimation method for an unknown covariance in cross-section adjustment based on unbiased and consistent estimator12
Applicability of differential die-away self-interrogation technique for quantification of spontaneous fission nuclides for fuel debris at Fukushima Daiichi Nuclear Power Plants12
Verification of human error traps in NPP procedures utilizing syntactic and semantic information extraction11
Development of a critical heat flux correlation based on a mechanistic model under subcooled flow boiling conditions11
Enhancement of random sampling by a combined approach of control variates and Latin hypercube sampling for uncertainty quantification in light water reactor lattice calculations11
Double diffusive dissolution model of UO2 pellet in molten Zr cladding11
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