JournalTOCs

Annals of Nuclear Energy
Journal Prestige (SJR): 1.41

Citation Impact (citeScore): 2
Number of Followers: 7

Hybrid journal (It can contain Open Access articles)
ISSN (Print) 0306-4549 - ISSN (Online) 1873-2100
Published by Elsevier

[2974 journals]

Fragility evaluation of nuclear containment structure subjected to
earthquake and subsequent internal pressure
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  Abstract: Publication date: March 2024Source: Annals of Nuclear Energy, Volume 197Author(s): Song Jin, Di Jiang, Dongmei Wang, Shaojie Wang, Zhen Wang
Gas phase interactions between tellurium and organic material in severe
nuclear accident scenarios
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  Abstract: Publication date: March 2024Source: Annals of Nuclear Energy, Volume 197Author(s): Anna-Elina Pasi, Teemu Kärkelä, Fredrik Börjesson Sandén, Unto Tapper, Tuula Kajolinna, Christian Ekberg
Numerical analysis of fluid force on orifice structure of valve disc for
nuclear globe valve
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  Abstract: Publication date: March 2024Source: Annals of Nuclear Energy, Volume 197Author(s): Ao Zhang, Qingye Li, Chaoyong Zong, Fuwen Liu, Tianhang Xue, Jian Xiao, Xueguan Song
Integration of Level 3 probabilistic risk assessment for nuclear power
plants with transportation simulation considering earthquake hazards
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  Abstract: Publication date: March 2024Source: Annals of Nuclear Energy, Volume 197Author(s): Kazumasa Shimada, Tatsuya Sakurahara, Pegah Farshadmanesh, Seyed Reihani, Zahra Mohaghegh
A predictor–corrector Monte Carlo method for thermal radiative
transfer equations
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  Abstract: Publication date: March 2024Source: Annals of Nuclear Energy, Volume 197Author(s): Yi Shi, Hui Xie
Accuracy analysis of RANS turbulent models on predicting thermal
stratification in the SUPERCAVNA facility
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  Abstract: Publication date: March 2024Source: Annals of Nuclear Energy, Volume 197Author(s): Wenbo Li, Yunqing Bai, Shuai Zhang, Yang Li, Ming Jin, Chunjing Li
Towards modelling defective fuel rods in TRANSURANUS: Benchmark and
assessment of gaseous and volatile radioactive fission product release
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  Abstract: Publication date: March 2024Source: Annals of Nuclear Energy, Volume 197Author(s): L. Giaccardi, M. Cherubini, G. Zullo, D. Pizzocri, A. Magni, L. Luzzi
On the need for multi-dimensional models for the safety analysis of
(fast-spectrum) Molten Salt Reactors
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  Abstract: Publication date: March 2024Source: Annals of Nuclear Energy, Volume 197Author(s): Nahom Habtemariam, Carlo Fiorina, Stefano Lorenzi, Antonio Cammi
Angular distribution uncertainty influence in a large sodium-cooled fast
reactor with mixed-oxide fuel
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  Abstract: Publication date: March 2024Source: Annals of Nuclear Energy, Volume 197Author(s): Alexander A. Ryzhkov, Georgy V. Tikhomirov, Mikhail Yu. Ternovykh
Enhancing the density and crush load of Li2TiO3 tritium breeding ceramic
pebbles by adding LiNO3-Li2CO3
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Yichao Gong, Qingze Na, Chao Dang, Yijiang Yang, Mingxiang Tang, Zhanwen Liu, Guojun Zhang
CFD analysis of curvature and inclination effect on steam condensation in
the presence of air
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Shuhang Zhou, Jianfa Li, Peixun Yang, Haozhi Bian, Ming Ding
Bicyclus: A statistical fuel cycle simulation framework for nuclear
verification
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Max Schalz, Lewin Bormann, Malte Göttsche
TARS: A parallel tetrahedral discontinuous finite element code for the
solution of the discrete ordinates neutron transport equation
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Guangchun Zhang, Hu Zhang
Effects of transient fission gas release on rod balloon burst behavior
during a loss-of-coolant accident
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Ian Greenquist, Nathan Capps
The influence of graphite moderator density on the neutronic performance
and fuel economy of a Molten Salt Reactor
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): R. Andika Putra Dwijayanto, Azizul Khakim, Zuhair, Andang Widi Harto
Development and verification of a one-dimensional collision probability
based neutron transport code to model axially heterogeneous cylindrical
vessels containing aqueous and organic plutonium nitrate
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): J.R. Daniels, M.M.R. Williams, M.D. Eaton
SN-MscaleDNN: A coupling approach for rapid shielding-scheme evaluation of
micro gas-cooled reactor in the large design-parameter space
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Kaihui Lei, Hongchun Wu, Zhouyu Liu, Yi Cao, Guoming Liu, Xiaojing Li, Qingming He, Liangzhi Cao
Extending TRANSURANUS burnup model for AGR-like FHR fuel design
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): A. de Lara, A. Schubert, E. Shwageraus, P. Van Uffelen
Testing of fiber optic based sensors for advanced reactors in the Texas
A&M University TRIGA reactor
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): J. Tyler Gates, Pavel V. Tsvetkov
FEMFFUSION and its verification using the C5G7 benchmark
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Y. Fontenla, A. Vidal-Ferràndiz, A. Carreño, D. Ginestar, G. Verdú
Iodine source term assessment under DBA SGTR accident scenario
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): A. Bousbia Salah, M. Di Giuli, P. Foucaud, R. Iglesias, A. Malkhasyan, M. Salmaoui, L.E. Herranz
233 U+comparing+ENDF/B-VII.1+and+ENDF/B-+VIII.0+libraries&rft.title=Annals+of+Nuclear+Energy&rft.issn=0306-4549&rft.date=&rft.volume=">Nuclear data sensitivity and uncertainty analysis using a set of
benchmarks containing 233 U comparing ENDF/B-VII.1 and ENDF/B- VIII.0
libraries
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): M. Hadouachi, H. Boukhal, El. Chakir, O. Belhaj, K. Laazouzi, H. El Yaakoubi, Abdelhamid Nouayti, T. El Ghalbzouri
Dependency analysis method for human failure events in level 2
probabilistic safety assessment of nuclear power plants
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Shuai Chen, Zehuan Zhang, Tao Qing, Li Zhang
Study on heat transfer characteristics of supercritical CO2/propane
mixtures in vertical tube
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Dandan Yin, Yunlong Zhou, Xintian Guo
Reflective reviews on Japanese high-level waste (HLW) vitrification –
Exploring the obstacles encountered in active tests at Rokkasho
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Akira Sakai, Shuichi Ishida
SCALE depletion capabilities for molten salt reactors and other
liquid-fueled systems
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Donny Hartanto, Friederike Bostelmann, Benjamin R. Betzler, Kursat B. Bekar, Shane W. Hart, William A. Wieselquist
Emission of the backscattered electron in the energy range of 20 to100 keV
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Aigen Xie, Yi-fan Liu, Hong-Jie Dong
The study on the main factors affecting the response analysis of nuclear
fuel transport cask drop
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Tianbao Lan, Qian Ren, Feng Sheng, Wei Tan
A numerical investigation of an indoor dry storage facility on heat
transfer
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Chia-Wei Lin, Yung-Shin Tseng, Kai-Qi Lin, Yu-Hsuan Chang, Tzu-Chen Hung, Hua-Yi Hsu
Investigation of aerosol transportation phenomena in pool scrubbing by
combining bubble plume measurements and single-bubble mass transfer
analysis
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Kota Fujiwara, Kohei Yoshida, Yuki Nakamura, Sasuke Kadoma, Akiko Kaneko, Yutaka Abe
Enhancing prediction accuracy for LOCA break sizes in nuclear power
plants: A hybrid deep learning method with data augmentation and
hyperparameter optimization
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Gui Zhou, Min-jun Peng, Hang Wang
Radiation damage analysis of the first generation VVER spent nuclear fuel
casks
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): M. Lovecký, J. Závorka, J. Jiřičková, R. Škoda
Expert knowledge modelling software design based on Signed Directed Graph
with the application for PWR fault diagnosis
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Zhanguo Ma, Shiguang Deng, Zhuoran Zhou, Xin Ai, Jing Zhang, Yongkuo Liu, Minjun Peng, Jing Cui
Multi-physics coupled analyzes of research nuclear reactors based on
steady-state and kinetics models
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Tengfei Zhang, Mingrui Yang, Chixu Luo, Hui He, Xiang Chai, Xiaojing Liu
Numerical study on thermal-hydraulic characteristics of lead-bismuth loop
system under moving conditions
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Lanfei Yuan, Zhipeng Liu, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su
Research on the influence of nonuniform inflow on steady-state hydraulic
performance of reactor coolant pump
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Jinqi Lu, Rui Xu, Yu Song, Song Huang, Junlian Yin, Dezhong Wang
Improvement of LLFPs transmutation efficiency by moderator loading in
lead-based fast neutron reactor
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Xiang-yang Sun, Hao-yang Lan, Liang-hua Han, Lie Liu
Subchannel thermal–hydraulic analysis of a wire-wrapped 19-pin rod
bundle in the NACIE-UP facility
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Rong Zhang, Dalin Zhang, Yu Liang, Jinshun Wang, Jian Deng, Xisi Zhang, Zhixin Niu, Wenxi Tian, Suizheng Qiu, Qi Luo
Distributed collaboration: Cognitive difference and collaborative decision
for multi-robot radioactive source search
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Minghua Luo, Jianwen Huo, Manlu Liu, Mingrun Ling, Xulin Hu
Parallelization and optimization for a pin-by-pin whole core
thermal–hydraulic analysis code
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Xiao Luo, Kefan Zhang, Junjia Zhang, Rui Pan, Aoguang Wu, Shuai Wang, Hongli Chen
Fast uncertainty quantification of spent nuclear fuel with neural networks
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Arnau Albà, Andreas Adelmann, Lucas Münster, Dimitri Rochman, Romana Boiger
Fault diagnosis of spent fuel shearing machines based on improved residual
network
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Wang Pingping, Chen Jiahua
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in
the EU-MUSA project
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): F. Mascari, A. Bersano, M. Massone, G. Agnello, O. Coindreau, S. Beck, L. Tiborcz, S. Paci, M. Angelucci, L.E. Herranz, R. Bocanegra, Y. Pontillon, M. Berdai, O. Cherednichenko, A. Iskra, M. Nudi, P. Groudev, P. Petrova, F. Kretzschmar, F. Gabrielli
Intelligent nuclear decommissioning solution: Code for site
characterization and management of overall surveys
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Hyungi Byun, Jong Dae Park, Sihyun An, Jinu Kim, Juyub Kim, Doo Yong Lee, Bongsoo Lee
Optimization analysis of thermal–hydraulic features of the 2.5 MW LBE
spallation target of CiADS
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Weiping Deng, Tao Wan, Weifeng Yang, Yongqin Ju, Fei Ma, Chengwen Qiang, Long Li, Fei Wang, Xueying Zhang
The technology of suppression containment for the SMR in floating nuclear
power plants against hydrogen risk
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Jialei Chen, Xuefeng Lyu, Fang Liu, Yu Yu, Fenglei Niu, Qingyao Song, Xichen Li
Numerical simulation and optimization of In-Vessel primary heat exchangers
of NHR200-II
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Geng Yiwa, Liu Xiongbin, Li Ziyi, Li Xiaotian, Zhang Yajun
Development of a site release category model and its application
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  Abstract: Publication date: February 2024Source: Annals of Nuclear Energy, Volume 196Author(s): Mina Cho, Dohyun Lim, Chanwoo Park, Moosung Jae