kw.\*:("Conjunto combustible")
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Numerical modeling of the shearing of irradiated fuel assembliesMESHCHERYAKOV, Yu. P.Journal of applied mechanics and technical physics. 2006, Vol 47, Num 3, pp 419-425, issn 0021-8944, 7 p.Article
The AFA 3G fuel assembly a proven design for high burnupsFORAT, C; FLORENTIN, F.TopFuel '99. International topical meetingSFEN /ENS conference. 1999, pp 73-82Conference Paper
Review and proposal for best fit of wire-wrapped fuel bundle friction factor and pressure drop predictions using various existing correlationsBUBELIS, E; SCHIKORR, M.Nuclear engineering and design. 2008, Vol 238, Num 12, pp 3299-3320, issn 0029-5493, 22 p.Article
Accurate Estimation of subcriticality using Indirect Bias Estimation method, (II) : ApplicationsSAKURAI, K; YAMAMOTO, T; ARAKAWA, T et al.Journal of Nuclear Science and Technology. 1997, Vol 34, Num 6, pp 544-550, issn 0022-3131Article
Automated fuel fabrication : A vision comes trueHEMANTHA RAO, G. V. S; PRAKASH, M. S; SETTY, C. R. P et al.Seminar on technological achievements. 1997, 4 p.Conference Paper
Nuclear analysis for the boraflex used in a typical spent-fuel storage assemblyINSOO JUN; MYUNG JAE SONG.Nuclear technology. 1995, Vol 109, Num 3, pp 357-365, issn 0029-5450Article
Effects of a new blending agent on ethanol-gasoline fuelsKARAOSMANOGLU, F; ISIGIGÜR, A; AKSOY, H. A et al.Energy & fuels. 1996, Vol 10, Num 3, pp 816-820, issn 0887-0624Article
Flooding in a thin rectangular slit geometry representative of ATR fuel assembly side-plate flow channelsLARSON, T. K; OH, C. H; CHAPMAN, J. C et al.Nuclear engineering and design. 1994, Vol 152, Num 1-3, pp 277-285, issn 0029-5493Article
Optimization of PWR fuel assembly radial enrichment and burnable poison location based on adaptive simulated annealingROGERS, Timothy; RAGUSA, Jean; SCHULTZ, Stephen et al.Nuclear engineering and design. 2009, Vol 239, Num 6, pp 1019-1029, issn 0029-5493, 11 p.Article
Thermohydraulic characteristics of an experimental fuel assembly for a water-graphite reactorDMITRIEV, A. M; GAVRILOV, P. M; TSYGANOV, A. A et al.Atomic energy (New York, N.Y.). 2006, Vol 101, Num 3, pp 669-674, issn 1063-4258, 6 p.Article
Calculation of a core with fuel elements whose cross sections are cross-shapedGROSHEVA, N. A; KIRSANOV, G. A; KONOPLEV, K. A et al.Atomic energy (New York, N.Y.). 2003, Vol 95, Num 1, pp 449-452, issn 1063-4258, 4 p.Article
Mapping of the lateral flow field in typical subchannels of a support grid with vanesMCCLUSKY, Heather L; HOLLOWAY, Mary V; CONOVER, Timothy A et al.Journal of fluids engineering. 2003, Vol 125, Num 6, pp 987-996, issn 0098-2202, 10 p.Article
Boundary condition for the adjoint flux corresponding to the flux discontinuity of the nodal diffusion equation in the perturbation theoryKOBAYASHI, K.Journal of Nuclear Science and Technology. 1998, Vol 35, Num 1, pp 20-25, issn 0022-3131Article
Resonance calculations using the multiband method and interface currentsTATSUMI, M; ITO, T; TAKEDA, T et al.Nuclear science and engineering. 1997, Vol 125, Num 2, pp 178-187, issn 0029-5639Article
Transuranium fuel assembly for transmutation in a pressurized water reactorMORI, M; KAWAMURA, M; YAMAMOTO, A et al.Nuclear technology. 1997, Vol 117, Num 2, pp 171-183, issn 0029-5450Article
Advanced mixed oxide fuel assemblies with higher plutonium contents for pressurized water reactorsBURTAK, F; HETZELT, L; STACH, W et al.Nuclear engineering and design. 1996, Vol 162, Num 2-3, pp 159-166, issn 0029-5493, 7 p.Article
Core stability tracking of the KKB BWR in recent yearsBLOMSTRAND, J; LÜDTKE, B; LUNDMARK, R et al.Nuclear engineering and design. 1995, Vol 154, Num 1, pp 27-41, issn 0029-5493Article
Dynamic analysis of AGR fuel assembliesNG, H. W.Computers & structures. 1995, Vol 54, Num 2, pp 339-350, issn 0045-7949Article
Monte-Carlo/collision probability hybrid method for LWR fuel assembly burnup calculationsKITADA, T; TAKEDA, T; SAJI, E et al.Journal of Nuclear Science and Technology. 1995, Vol 32, Num 7, pp 683-690, issn 0022-3131Article
Experimental investigation of role of burn-up for local fault propagation in LMR fuel assembliesSCHLEISIEK, K; ABERLE, J; SCHMUCK, I et al.Journal of Nuclear Science and Technology. 1994, Vol 31, Num 10, pp 1011-1022, issn 0022-3131Article
SCALE calculation for evaluation of spent fuel condition during long-term storageMIKLOS, M; SLUGEN, V.Nuclear engineering and design. 2008, Vol 238, Num 10, pp 2811-2814, issn 0029-5493, 4 p.Article
On the geometry of the fuel rod supports concerning a fretting wear failureKIM, Hyung-Kyu; LEE, Young-Ho; LEE, Kang-Hee et al.Nuclear engineering and design. 2008, Vol 238, Num 12, pp 3321-3330, issn 0029-5493, 10 p.Article
SIMULATION OF NUCLEAR-PHYSICAL PROCESSES IN THE SURFACE LAYER OF A FUEL KERNEL WITH A CONSUMABLE ABSORBERBARANOV, V. G; TEMOVYKH, M. Yu; TIKHOMIROV, G. V et al.Atomic energy (New York, N.Y.). 2008, Vol 105, Num 6, pp 391-396, issn 1063-4258, 6 p.Article
Re-establishment of the continuity of knowledge in the safeguards of interim storages using NDA techniquesPEERANI, P; GALLETTA, M.Nuclear engineering and design. 2007, Vol 237, Num 1, pp 94-99, issn 0029-5493, 6 p.Article
Effect of radial void distribution within fuel assembly on assembly neutronic characteristicsAMA, Tsuyoshi; HYOUDOU, Hideaki; TAKEDA, Toshikazu et al.Journal of Nuclear Science and Technology. 2002, Vol 39, Num 1, pp 90-100, issn 0022-3131Article