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92 results found

no	title	author	magazine	year	volume	issue	page(s)	type
1	Adsorption of uranium(VI) from sulphate solutions using Amberlite IRA-402 resin: Equilibrium, kinetics and thermodynamics study	Solgy, Mostafa		2015	75	C	p. 132-138	article
2	Analysis of anticipated transient without scram of a Super Fast Reactor with single flow pass core	Sutanto,		2015	75	C	p. 54-63	article
3	Analysis of flow and heat transfer in a new lattice	Xiao, Hongguang		2015	75	C	p. 536-541	article
4	Analysis of Phenix End-of-Life asymmetry test with multi-dimensional pool modeling of MARS-LMR code	Jeong, H.-Y.		2015	75	C	p. 443-451	article
5	Analysis on isotopic plutonium barrier based on spent nuclear fuel of LWR	Permana, Sidik		2015	75	C	p. 116-122	article
6	A new mathematical adjoint for the modified SAAF- S N equations	Schunert, Sebastian		2015	75	C	p. 340-352	article
7	A new methodology for estimation of initial entrainment fraction in annular flow for improved dryout prediction	Dasgupta, A.		2015	75	C	p. 323-330	article
8	Application of Continuous and Structural ARMA modeling for noise analysis of a BWR coupled core and plant instability event	Demeshko, M.		2015	75	C	p. 645-657	article
9	AP1000® SBLOCA simulations with TRACE code	Montero-Mayorga, J.		2015	75	C	p. 87-100	article
10	A unified generic theory on discontinuity factors in diffusion, SP3 and transport calculations	Yu, Lulin		2015	75	C	p. 239-248	article
11	BRAHMMA: A compact experimental accelerator driven subcritical facility using D-T/D-D neutron source	Sinha, Amar		2015	75	C	p. 590-594	article
12	CFD analysis of flow and heat transfer in Canadian supercritical water reactor bundle	Podila, K.		2015	75	C	p. 1-10	article
13	CHF prediction model research for flat and hypervapotron heating surface in subcooled flow nucleate boiling	Lin, Meng		2015	75	C	p. 581-589	article
14	Commercial thorium fuel manufacture and irradiation: Testing (Th,Pu) O 2 and (Th,U) O 2 in the “Seven-Thirty” program	Insulander Björk, Klara		2015	75	C	p. 79-86	article
15	Comparison of algorithms for Doppler broadening pointwise tabulated cross sections	Romano, Paul K.		2015	75	C	p. 358-364	article
16	Conceptual design of a passively safe thorium breeder Pebble Bed Reactor	Wols, F.J.		2015	75	C	p. 542-558	article
17	Coupling of system thermal–hydraulics and Monte-Carlo code: Convergence criteria and quantification of correlation between statistical uncertainty and coupled error	Wu, Xu		2015	75	C	p. 377-387	article
18	Critical flow maps using an extended Henry–Fauske model	Kim, Yeon-Sik		2015	75	C	p. 516-520	article
19	Critical mass calculations using MCNP: An academic exercise	Kastanya, Doddy		2015	75	C	p. 228-231	article
20	CUDA and MPI performances on the computation of Rossi-α distribution from pulsed neutron sources	Talamo, Alberto		2015	75	C	p. 168-175	article
21	Detailed evaluation of melt pool configuration in the lower plenum of the APR1400 reactor vessel during severe accidents	Park, Rae-Joon		2015	75	C	p. 476-482	article
22	Determination of total mass attenuation coefficients, effective atomic numbers and electron densities for different shielding materials	Elmahroug, Y.		2015	75	C	p. 268-274	article
23	Development of a phenomena identification ranking table for simulating a station blackout transient of a pressurized water reactor with a thermal-hydraulic integral effect test facility	Kang, Kyoung-Ho		2015	75	C	p. 72-78	article
24	Development of semi-empirical model for tritium permeation under non-uniform temperature distribution at heat exchanger tube wall	Park, Min Young		2015	75	C	p. 413-420	article
25	Dry storage of spent nuclear fuel in UAE – Economic aspect	Al Saadi, Sara		2015	75	C	p. 527-535	article
26	3D simulations of the hydrodynamic deformation of melt droplets in a water pool	Thakre, Sachin		2015	75	C	p. 123-131	article
27	Editorial board			2015	75	C	p. IFC	article
28	Editors’ note	Williams, M.M.R.		2015	75	C	p. 752	article
29	Effect of geometric factors on performance of a sodium to air heat exchanger in a fast breeder reactor	Kannan, K.		2015	75	C	p. 428-437	article
30	Estimation of neutronics parameter sensitivity to nuclear data in random sampling-based uncertainty quantification calculations	Chiba, Go		2015	75	C	p. 395-403	article
31	Evaluation of interfacial area transport equation in vertical bubbly two-phase flow in large diameter pipes	Tian, Daogui		2015	75	C	p. 199-209	article
32	Evaluation of parameterization schemes in the Weather Research and Forecasting (WRF) model: A case study for the Kaiga nuclear power plant site	Shrivastava, R.		2015	75	C	p. 693-702	article
33	Experimental investigation of void distribution in suppression pool over the duration of a loss of coolant accident using steam–water two-phase mixture	Rassame, Somboon		2015	75	C	p. 570-580	article
34	Experimental investigation on pressure oscillation frequency for submerged sonic/supersonic steam jet	Qiu, Binbin		2015	75	C	p. 388-394	article
35	Experimental research on the thermal hydraulic characteristics of liquid sodium flowing in annuli with low Peclet number	Qiu, Zicheng		2015	75	C	p. 483-491	article
36	Experimental validation of RELAP5 predictions for subcooled leak flow through narrow circumferential slits	Ghosh, Sandip		2015	75	C	p. 507-515	article
37	Explicit appropriate basis function method for numerical solution of stiff systems	Chen, Wenzhen		2015	75	C	p. 353-357	article
38	Features of a subcritical nuclear reactor	Vega-Carrillo, Hector Rene		2015	75	C	p. 101-106	article
39	Higher order sliding mode controller design for a research nuclear reactor considering the effect of xenon concentration during load following operation	Ansarifar, G.R.		2015	75	C	p. 728-735	article
40	Investigation of molten core–concrete interaction reactor benchmark test for VVER 1000	Stefanova, A.		2015	75	C	p. 742-751	article
41	Investigation of the Self-Interrogation Neutron Resonance Densitometry applied to spent fuel using Monte Carlo simulations	Rossa, Riccardo		2015	75	C	p. 176-183	article
42	Investigation of trans-critical CO2 horizontal mini-channel flow with multi-peak heat transfer behaviors	Chen, Lin		2015	75	C	p. 559-569	article
43	Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor	Tusheva, P.		2015	75	C	p. 249-260	article
44	Linkage options between unit process to enhance proliferation resistance of pyroprocessing	Ahn, Seong-Kyu		2015	75	C	p. 184-188	article
45	Measurement of multiple α-modes at the Delphi subcritical assembly by neutron noise techniques	Szieberth, Máté		2015	75	C	p. 146-157	article
46	Methodology for the scoping assessment of radioactive releases during dismantling of RBMK-1500 reactor systems with low-level contamination	Ragaišis, Valdas		2015	75	C	p. 193-198	article
47	Modeling droplet-laden flows in moisture separators using k-d trees	Zhang, Huang		2015	75	C	p. 452-461	article
48	Modeling scheme of the Safety Injection Tank with Fluidic Device for best estimate calculation of LBLOCA	Bang, Young Seok		2015	75	C	p. 605-610	article
49	Monte Carlo methods for reactor period calculations	Zoia, Andrea		2015	75	C	p. 627-634	article
50	Multicriteria decision analysis based on analytic hierarchy process in GIS environment for siting nuclear power plant in Egypt	Abudeif, A.M.		2015	75	C	p. 682-692	article
51	Negative pressure difference evaluation of Lungmen ABWR containment by using GOTHIC	Chen, Yen-Shu		2015	75	C	p. 672-681	article
52	Neutron batch size optimisation methodology for Monte Carlo criticality calculations	Tuttelberg, Kaur		2015	75	C	p. 620-626	article
53	Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors	George, Nathan Michael		2015	75	C	p. 703-712	article
54	Neutronic parameters of a low enrichment core in reactor LR-0 for MSR research	Košt’ál, Michal		2015	75	C	p. 316-322	article
55	Neutronics calculations for denatured molten salt reactors: Assessing resource requirements and proliferation-risk attributes	Ahmad, Ali		2015	75	C	p. 261-267	article
56	Neutron irradiation performance of Zircaloy-4 under research reactor operating conditions	Jin, Hyun Ju		2015	75	C	p. 309-315	article
57	Neutron kerma coefficients of compounds for shielding and dosimetry	Singh, Vishwanath P.		2015	75	C	p. 189-192	article
58	Novel passive and active tungsten-based identifiers for maintaining the continuity of knowledge of spent nuclear fuel copper canisters	Chernikova, Dina		2015	75	C	p. 219-227	article
59	Nuclear data sensitivity and uncertainty for the Canadian supercritical water-cooled reactor II: Full core analysis	Langton, S.E.		2015	75	C	p. 635-644	article
60	Nuclear waste transmutation performance assessment of an accelerator driven subcritical reactor for waste transmutation (ADS-NWT)	Chen, Zhong		2015	75	C	p. 723-727	article
61	Numerical simulation of temperature fluctuation reduction by a vortex breaker in an elbow pipe with thermal stratification	Lu, T.		2015	75	C	p. 462-467	article
62	NUSS: A tool for propagating multigroup nuclear data covariances in pointwise ACE-formatted nuclear data using stochastic sampling method	Zhu, Ting		2015	75	C	p. 713-722	article
63	On the second moment of a stochastic radiation field	Ayyoubzadeh, Seyed Mohsen		2015	75	C	p. 283-291	article
64	Operation characteristic of Integrated Pressurized Water Reactor under coordination control scheme	Du, Xue		2015	75	C	p. 658-664	article
65	Optimization method for the design of hexagonal fuel assemblies	Qvist, Staffan		2015	75	C	p. 498-506	article
66	Parameterized representation of macroscopic cross section for PWR reactor	Fiel, João Cláudio Batista		2015	75	C	p. 736-741	article
67	Preliminary studies of compact Brayton cycle performance for Small Modular High Temperature Gas-cooled Reactor system	Bae, Seong Jun		2015	75	C	p. 11-19	article
68	Pressurized water reactor in-core nuclear fuel management by tabu search	Hill, Natasha J.		2015	75	C	p. 64-71	article
69	Prototypic corium oxidation and hydrogen release during the Fuel–Coolant Interaction	Tyrpekl, Vaclav		2015	75	C	p. 210-218	article
70	Publisher Note			2015	75	C	p. iii	article
71	Quantification of in-containment fission products source term for 1000MWe PWR under loss of coolant accident	Mehboob, Khurram		2015	75	C	p. 365-376	article
72	Radiocarbon mass balance for a Magnox nuclear power station	Metcalfe, M.P.		2015	75	C	p. 665-671	article
73	Research of flow instability in OTSG under low load conditions	Xia, Genglei		2015	75	C	p. 421-427	article
74	Safety, security and safeguard	Zakariya, Nasiru Imam		2015	75	C	p. 292-302	article
75	Scaling analysis for the ocean motions in single phase natural circulation	Yan, B.H.		2015	75	C	p. 521-526	article
76	Seed and blanket thorium-reprocessed fuel ADS: Multi-cycle approach for higher thorium utilization and TRU transmutation	Vu, Thanh Mai		2015	75	C	p. 438-442	article
77	Sensitivity and uncertainty analysis for UO 2 and MOX fueled PWR cells	Foad, Basma		2015	75	C	p. 595-604	article
78	Simulation of boiling flow in evaporator of separate type heat pipe with low heat flux	Kuang, Y.W.		2015	75	C	p. 158-167	article
79	Sliding mode control design for a PWR nuclear reactor using sliding mode observer during load following operation	Ansarifar, G.R.		2015	75	C	p. 611-619	article
80	Solution of the OECD/NEA neutronic SFR benchmark with Serpent-DYN3D and Serpent-PARCS code systems	Nikitin, E.		2015	75	C	p. 492-497	article
81	Study of power distribution in the CZP, HFP and normal operation states of VVER-1000 (Bushehr) nuclear reactor core by coupling nuclear codes	Rafiei Karahroudi, Mohsen		2015	75	C	p. 38-43	article
82	Subchannel analysis of fuel temperature and departure of nucleate boiling of TRIGA Mark I	Johns, Jesse		2015	75	C	p. 331-339	article
83	The effect of changing enrichments on core performance	Levine, S.		2015	75	C	p. 139-145	article
84	The effect of coolant quantity on local fuel–coolant interactions in a molten pool	Cheng, Songbai		2015	75	C	p. 20-25	article
85	The Laputa code for lattice physics analyses	She, Ding		2015	75	C	p. 303-308	article
86	The time dependence of the extinction probability with delayed neutrons	Williams, M.M.R.		2015	75	C	p. 107-115	article
87	Transient performance analysis of pressurized safety injection tank with a partition	Bae, Youngmin		2015	75	C	p. 232-238	article
88	Transient thermal–hydraulic analysis of complete single channel blockage accident of generic 10MW research reactor	Son, Hyung Min		2015	75	C	p. 44-53	article
89	Uncertainty and correlation analysis of lead nuclear data on reactor parameters for the European Lead Cooled Training Reactor	Alhassan, E.		2015	75	C	p. 26-37	article
90	Using high temperature gas-cooled reactors for greenhouse gas reduction and energy neutral production of phosphate fertilizers	Haneklaus, Nils		2015	75	C	p. 275-282	article
91	Verification of SAMG entry condition for APR1400	Yun, Junghyun		2015	75	C	p. 404-412	article
92	Whole-core transport solution via deterministic SN transport/p-CMFD overlapping local/global calculation in hexagonal geometry problem	Yoo, Han Jong		2015	75	C	p. 468-475	article

92 results found

Koninklijke Bibliotheek - National Library of the Netherlands