Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
《核能年鉴》为交流核能科学和技术领域所有领域的原创研究、想法和发展提供了一个国际媒介。其范围包括核燃料储备、燃料循环和成本、材料、加工、系统和组件技术（仅裂变）、设计和优化、核能源直接转换、环境控制、反应堆物理、传热和流体动力学、结构分析、燃料管理、未来发展、核燃料和安全、核气溶胶、中子物理、计算机技术（包括软件和硬件）、风险评估、放射性废物处置和反应堆热工水力学。提交给Annals的论文需要证明与核能发电/核工程的明确联系。涉及纯核物理、纯健康物理、成像或混凝土和各种地质材料的衰减和屏蔽特性的论文不在本杂志的范围之内。此外，涉及政策或经济学的论文也不在该杂志的范围之内。
Narrowing transient testing pulse widths to enhance LWR RIA experiment design in the TREAT facility
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.10.030
Numerical study of thermal hydraulics behavior on the integral test facility for passive containment cooling system using GASFLOW-MPI
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.09.014
Re-assessment of station blackout accident in VVER-1000 NPP with additional measures following Fukushima accident using Relap/Mod3.2
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.02.006
GPU accelerated lattice Boltzmann method in neutron kinetics problems
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.02.009
Transient analysis of C5G7-TD benchmark with MPACT
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.10.049
Minor Actinides transmutation in candidate accident tolerant fuel-claddings U3Si2-FeCrAl and U3Si2-SiC
来源期刊：Annals of Nuclear EnergyDOI：10.1016/j.anucene.2018.12.003
A leakage correction with SPH factors for two-group constants in GET-based pin-by-pin reactor analyses
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.01.032
Effect of kinetics parameters on transients calculations in external source driven subcritical VR-1 reactor
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.09.007
The thermal hydraulic phenomenon in tight lattice bundles: A review
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.11.037
Stability analysis of the CMFD scheme with linear prolongation
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.02.011
Control rod treatment for FEM based radiation transport methods
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.11.054
Sensitivity methods for effective delayed neutron fraction and neutron generation time with summon
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.11.042
Neutronic analysis of thorium MOX fuel blocks with different driver fuels in advanced block-type HTRs
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.01.049
Phenomena Identification and Ranking Table (PIRT) study for metallic structural materials for advanced High-Temperature reactor
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.08.036
Uncertainty analysis of rod ejection accident in VVER-1000 reactor
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.06.061
Analysis of start-up and long-term operation characteristics of passive residual heat removal system
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.02.033
Neutronics performance analysis on neutron consumption in a Fusion-Fission Hybrid System for tritium breeding
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.10.042
Spatial decomposition of structured grids for nuclear reactor simulations
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.06.054
Study on neutronics of VVER-1200 with accident tolerant fuel cladding
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.10.040
Calculation of the cross and auto power spectral densities for low neutron counting from pulse mode detectors
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.03.032
Overall thermal-hydraulic behavior in an SBO test using HSIT in the ATLAS facility
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.02.050
Wilks’ formula applied to computational tools: A practical discussion and verification
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.05.012
Analysis of the stochastic point reactor using Wiener-Hermite expansion
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.06.022
An experimental study on debris bed formation behavior at bottom-heated boiling condition
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.10.003
The numerical solution of space-dependent neutron kinetics equations in hexagonal-z geometry using backward differentiation formula with adaptive step size
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.01.004
Detached eddy simulation of turbulent and thermal mixing in a T-junction
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.10.006
Natural circulation flow resistance correlations in a rod bundle channel under vertical, inclined and rolling motion conditions
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.02.031
Scaling and integral effect test on transition from depressurization to long-term gravity injection
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.01.034
A quasi-static Monte Carlo algorithm for the simulation of sub-prompt critical transients
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.11.055
A combined immersed body and adaptive mesh method for simulating neutron transport within complex structures
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.05.044
Analytical solution for the Doppler broadening function using the Kaniadakis distribution
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.11.023
Experimental and numerical study on helium flow characteristics in randomly packed pebble bed
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.01.016
Physics characteristics of internally cooled annular fuel for potential application in pressure tube heavy water reactors
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.10.028
Ultrasonic high frequency guided wave for detection and identification of defect location in seal welds of sodium cooled fast reactor fuel subassemblies
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.06.064
Development of the RAINBOW code to evaluate assembly bowing reactivity coefficients in sodium-cooled fast reactors
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.02.004
A robust multi phase model to investigate molten material relocation during total flow blockage in SFR fuel subassembly
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.05.007
A rehomogenization-based approach to model spectral effects of local nuclide density changes in nodal calculations
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.10.061
Establishing safety goals on radiation protection for a space reactor through a case assessment of a loss-of-coolant accident in the International Space Station
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.06.016
Covariance-oriented sample transformation: A new sampling method for reactor-physics uncertainty analysis
来源期刊：Annals of Nuclear EnergyDOI：10.1016/j.anucene.2019.07.001
Fuel management code system against experimental measurements of the CMRR reactor
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.02.038
Boiling water cooled travelling wave reactor
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.06.037
Uncertainty quantification of LWR-PROTEUS Phase II experiments using CASMO-5
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.03.023
Analysis and application on sensitivity factors of cross validation of fill rate of CPR1000 unit reactor core coolant monitoring system
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.05.038
An adaptive probabilistic mapping matrix search algorithm for vulnerability analysis of PPS
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.04.013
Core analysis of spectral shift operated SmAHTR
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.09.013
Investigation on the impact of thermal-kernel effect of lithium hydride on the reactivity of nuclear propulsion particle bed reactor
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.12.039
Nth-order multi-response CADIS method to optimize regional variances in a hybrid Monte Carlo simulation
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2018.11.018
Prediction of flow distribution of vertical upward co-current adiabatic annular flow in 8 × 8 rod bundle
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.06.040
An accelerated synchronized forward-adjoint approach in method of characteristics neutron transport solution
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.07.029
Neutronic simulations for the FRM II
来源期刊：Annals of Nuclear EnergyDOI：10.1016/J.ANUCENE.2019.03.010
