International Journal of Hydrogen Energy

International Journal of Hydrogen Energy, Vol.41, No.17 Entire volume, number list

ISSN: 0360-3199 (Print)

In this Issue (35 articles)

6981 - 6983	Preface to the special issue on "17th International Conference on Emerging Nuclear Energy Systems (ICENES'2015), 4-8 October 2015, Istanbul, Turkey" Sahin S, Sahin HM, Martinez-Val J, Wu YC
6984 - 6989	Comparative studies on plutonium utilization in HTTR with helium and carbon dioxide gas coolants Waris A, Prastyo PA, Pramuditya S, Irwanto D, Sekimoto H
6990 - 6995	A review on the application of liquid metals as heat transfer fluid in Concentrated Solar Power technologies Lorenzin N, Abanades A
6996 - 7004	The contribution of wind-hydro pumped storage systems in meeting Lebanon's electricity demand Al Zohbi G, Hendrick P, Renier C, Bouillard P
7005 - 7018	Preliminary studies of a new permanent magnet generator (PMG) with the axial and radial flux morphology Gor H, Kurt E
7019 - 7026	Electromagnetic design of a new axial and radial flux generator with the rotor back-irons Kurt E, Gor H, Doner U
7027 - 7035	Numerical study of mass transfer coefficient in a T-junction Erfaninia A, Nematollahi M
7036 - 7046	CFX study of flow accelerated corrosion via mass transfer coefficient calculation in a double elbow Keshtkar K, Nematollahi M, Erfaninia A
7047 - 7052	Preliminary steady state and transient thermal analysis of the new HCPB blanket for EU DEMO reactor Zhou GM, Hernandez F, Boccaccini LV, Chen HL, Ye MY
7053 - 7058	Preliminary structural analysis of the new HCPB blanket for EU DEMO reactor Zhou GM, Hernandez F, Boccaccini LV, Chen HL, Ye MY
7059 - 7068	Accident analysis of tungsten target coupled with ADS core Peng TJ, Lang MG, Zhou ZW, Gu L
7069 - 7075	Investigation of tritium breeding ratio using different coolant material in a fusion-fission hybrid reactor Sahin HM, Tunc G, Sahin N
7076 - 7081	Reactor core and actinide production evaluation based on different loading material of recyled spent nuclear fuel of LWR in FBR Permana S, Saputra G, Suzuki M, Suud Z, Saito M
7082 - 7093	A sodium-cooled ultra-long-life reactor core having improved inherent safety with new driver-blanket burning strategy Hyun H, Hong SG
7094 - 7102	Thorium utilization in existing and advanced reactor types Jagannathan V, Mathur A, Khan SA
7103 - 7111	Assessment of thermal hydraulics parameters of the VVER-1000 during transient conditions Bagheri S, Faghihi F, Nematollahi MR, Behzadinejad B
7112 - 7118	Asymptotic radial fuel shuffling mode for accelerator driven transmuter Chen XN, Rineiski A
7119 - 7125	Effects of moisture on thermal conductivity of the lightened construction material Belkharchouche D, Chaker A
7126 - 7131	Impact of the Bell-Plesset instability on centralized sloshing in pool geometry Li R, Maschek W, Boccaccini CM, Vezzoni B, Flad M, Rineiski A
7132 - 7138	GANEX and UREX plus reprocessed fuels in ADS Barros G, Velasquez C, Pereira C, Veloso MA, Costa A
7139 - 7145	Characteristics of flow field and pressure fluctuation in complex turbulent flow in the third elbow of a triple elbow piping with small curvature radius in three-dimensional layout Ebara S, Takamura H, Hashizume H, Yamano H
7146 - 7157	Heat recovery process in an adsorption refrigeration machine Chekirou W, Boukheit N, Karaali A
7158 - 7168	Conceptual design of a small modular natural circulation lead cooled fast reactor SNCLFR-100 Chen HL, Chen Z, Chen C, Zhang XL, Zhang HR, Zhao PC, Shi KL, Li SZ, Feng JC, Zeng Q
7169 - 7174	Performance improvement of adsorption solar cooling system Chekirou W, Boukheit N, Karaali A
7175 - 7180	Studies of MYRRHA using thorium fuel Barlow R, Burlison J, Edwards T, Healy A, Masterson A, Abderrahim HA, Malambu E, van den Eynde G
7181 - 7184	Producing Hydrogen-3 by irradiating lithium orthosilicate targets in a fission research reactor Hadad K, Jabbari M, Tabadar Z, Hashemi-Tilehnoee M
7185 - 7191	Effect of swirl number on combustion characteristics of hydrogen-containing fuels in a combustor Ilbas M, Karyeyen S, Yilmaz I
7192 - 7196	HTR steady state and transient thermal analyses Scari ME, Costa AL, Pereira C, Velasquez CE, Veloso MAF
7197 - 7205	Uncertainties in energy and exergy efficiency of a High Pressure Turbine in a thermal power plant Ege A, Sahin HM
7206 - 7212	Use of tungsten single crystals to enhance nuclear reactors structural elements properties Solntceva ES, Taubin ML, Bochkov NA, Solntsev VA, Yaskolko AA
7213 - 7220	Radiation source terms of MYRRHA reactor components and equipment Celik Y, Stankovskiy A, Engelen J, Van den Eynde G, Sarer B, Sahin S
7221 - 7226	Moderation and shielding optimization for a Cf-252 based prompt gamma neutron activation analyzer system Hadad K, Nematollahi M, Sadeghpour H, Faghihi R
7227 - 7232	Numerical investigation of SIMMER code for fuel-coolant interaction Guo LC, Li R, Wang SS, Flad M, Maschek W, Rineiski A
7233 - 7238	Evaluation of influence of the inlet swirling flow on the flow field in a triple elbow system Mizutani J, Ebara S, Hashizume H
7239 - 7251	Small scale experiments of sloshing considering the seismic safety of MYRRHA Myrillas K, Planquart P, Buchlin JM, Schyns M