EPR : conception du coeur et combustibleCORNILUS, Pierre-Louis; FRANCILLON, Eric; KIEHLMANN, Horst Dieter et al.Revue générale nucléaire. 2004, Num 6, pp 55-60, issn 0335-5004, 6 p.Conference Paper

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

A US perspective on fast reactor fuel fabrication technology and experience part I: metal fuels and assembly designBURKES, Douglas E; FIELDING, Randall S; PORTER, Douglas L et al.Journal of nuclear materials. 2009, Vol 389, Num 3, pp 458-469, issn 0022-3115, 12 p.Article

Burnup effect on ⁹⁵Nb/⁹⁵Zr ratio-cooling time correlationHADDAD, Kh.Journal of nuclear materials. 2005, Vol 345, Num 1, pp 86-88, issn 0022-3115, 3 p.Article

Verifying the thermohydraulic codes using the standard problem of bottom refloodingEFANOV, A. D; VINOGRADOV, V. N; GAL'CHENKO, E. F et al.Thermal engineering. 2003, Vol 50, Num 11, pp 891-896, issn 0040-6015, 6 p.Article

Numerical study of coolant mixing caused by the flow deflectors in a nuclear fuel bundleWANG KEE IN.Nuclear technology. 2001, Vol 134, Num 2, pp 187-195, issn 0029-5450Article