Annals of Nuclear Energy

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Top Articles

#	Title	Journal	Year	Citations
1	The Serpent Monte Carlo code: Status, development and applications in 2013	Annals of Nuclear Energy	2015	897
2	Calculation of radiation attenuation coefficients for shielding concretes	Annals of Nuclear Energy	1997	749
3	Overview of the FLUKA code	Annals of Nuclear Energy	2015	540
4	OpenMC: A state-of-the-art Monte Carlo code for research and development	Annals of Nuclear Energy	2015	446
5	CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC	Annals of Nuclear Energy	2015	315
6	The OpenMC Monte Carlo particle transport code	Annals of Nuclear Energy	2013	278
7	Photon attenuation coefficients of concrete includes barite in different rate	Annals of Nuclear Energy	2010	266
8	TRIPOLI-4®, CEA, EDF and AREVA reference Monte Carlo code	Annals of Nuclear Energy	2015	241
9	RMC – A Monte Carlo code for reactor core analysis	Annals of Nuclear Energy	2015	215
10	Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1	Annals of Nuclear Energy	1999	206
11	General solution of Bateman equations for nuclear transmutations	Annals of Nuclear Energy	2006	193
12	Nuclear data sensitivity, uncertainty and target accuracy assessment for future nuclear systems	Annals of Nuclear Energy	2006	191
13	Effective atomic and electron numbers of some steels at different energies	Annals of Nuclear Energy	2009	184
14	Physics-based multiscale coupling for full core nuclear reactor simulation	Annals of Nuclear Energy	2015	184
15	Gamma ray and neutron shielding properties of some concrete materials	Annals of Nuclear Energy	2011	179
16	Towards the thorium fuel cycle with molten salt fast reactors	Annals of Nuclear Energy	2014	162
17	Gamma ray and neutron shielding properties of some alloy materials	Annals of Nuclear Energy	2014	159
18	Determination and calculation of gamma and neutron shielding characteristics of concretes containing different hematite proportions	Annals of Nuclear Energy	2011	158
19	Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors	Annals of Nuclear Energy	2015	155
20	A survey of dynamic methodologies for probabilistic safety assessment of nuclear power plants	Annals of Nuclear Energy	2013	151
21	Gamma radiation shielding and optical properties measurements of zinc bismuth borate glasses	Annals of Nuclear Energy	2014	150
22	Calculation of fast neutron removal cross-sections for some compounds and materials	Annals of Nuclear Energy	2010	144
23	Comparative study of silicate glasses containing Bi2O3, PbO and BaO: Radiation shielding and optical properties	Annals of Nuclear Energy	2011	143
24	The effect of barite proportion on neutron and gamma-ray shielding	Annals of Nuclear Energy	2013	143
25	Investigation on radiation shielding parameters of bismuth borosilicate glass from 1keV to 100GeV	Annals of Nuclear Energy	2013	141
26	Kinetic and thermodynamic studies of uranium(VI) adsorption using Amberlite IRA-910 resin	Annals of Nuclear Energy	2012	140
27	Towards sustainable nuclear energy: Putting nuclear physics to work	Annals of Nuclear Energy	2008	139
28	Recent progress of CFD applications in PWR thermal hydraulics study and future directions	Annals of Nuclear Energy	2021	137
29	Gamma-ray mass attenuation coefficient and half value layer factor of some oxide glass shielding materials	Annals of Nuclear Energy	2016	136
30	Development strategy and conceptual design of China Lead-based Research Reactor	Annals of Nuclear Energy	2016	135
31	Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers	Annals of Nuclear Energy	2013	132
32	Comparison of shielding properties for ordinary, barite, serpentine and steel–magnetite concretes using MCNP-4C code and available experimental results	Annals of Nuclear Energy	2013	124
33	Comparative study of different concrete composition as gamma-ray shielding materials	Annals of Nuclear Energy	2015	123
34	Fractional neutron point kinetics equations for nuclear reactor dynamics	Annals of Nuclear Energy	2011	120
35	Features of MCNP6	Annals of Nuclear Energy	2016	119
36	Numerical simulation of heat transfer deterioration phenomenon in supercritical water through vertical tube	Annals of Nuclear Energy	2010	113
37	A new high-fidelity neutronics code NECP-X	Annals of Nuclear Energy	2018	113
38	Gamma-rays shielding properties of xPbO:(100−x)B2O3 glasses system at 662keV	Annals of Nuclear Energy	2009	111
39	Study of photon interactions and shielding properties of silicate glasses containing Bi2O3, BaO and PbO in the energy region of 1keV to 100GeV	Annals of Nuclear Energy	2012	111
40	The OpenMOC method of characteristics neutral particle transport code	Annals of Nuclear Energy	2014	111
41	A simplified method for heat transfer prediction of supercritical fluids in circular tubes	Annals of Nuclear Energy	2009	110
42	Study on adsorption performance of coal based activated carbon to radioactive iodine and stable iodine	Annals of Nuclear Energy	2014	108
43	Generalized Monte Carlo perturbation algorithms for correlated sampling and a second-order Taylor series approach	Annals of Nuclear Energy	1984	105
44	Biases in the estimation of Keff and its error by Monte Carlo methods	Annals of Nuclear Energy	1986	104
45	Prediction of turbulent convective heat transfer to a fluid at supercritical pressure in square and triangular channels	Annals of Nuclear Energy	2008	104
46	The technology of micro heat pipe cooled reactor: A review	Annals of Nuclear Energy	2020	104
47	Calculation of the cross-sections for fast neutrons and gamma-rays in concrete shields	Annals of Nuclear Energy	2002	103
48	Efficient numerical solution of the point kinetics equations in nuclear reactor dynamics	Annals of Nuclear Energy	2004	103
49	Variation of energy absorption buildup factors with incident photon energy and penetration depth for some commonly used solvents	Annals of Nuclear Energy	2008	103
50	Sustainability of electricity supply technology portfolio	Annals of Nuclear Energy	2009	102

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