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Measurement of pressure drop in a full-scale fuel assembly of a liquid metal reactorKI CHOI, Seok; KON CHOI, Il; YUN NAM, Ho et al.Journal of pressure vessel technology. 2003, Vol 125, Num 2, pp 233-238, issn 0094-9930, 6 p.Article

Two-dimensional geometrical corner singularities in neutron diffusion-part II : Application to the SNR-300 BenchmarkCACUCI, D. G; KIEFHABER, E; STEHLE, B et al.Nuclear science and engineering. 1998, Vol 128, Num 1, pp 17-26, issn 0029-5639Article

Automated calculation of fission events in experiments on critical assembliesGULNIK, O. I; ZHUK, I. V; MALYKHIN, A. P et al.Nuclear tracks and radiation measurements (1993). 1993, Vol 21, Num 3, pp 387-390, issn 0969-8078Conference 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

A high-breeding fast reactor with fission product gas purge/tube-in-shell metallic fuel assembliesHIRAOKA, T; SAKO, K; TAKANO, H et al.Nuclear technology. 1991, Vol 93, Num 3, pp 305-329, issn 0029-5450, 25 p.Article

Activities of a fuel supplier for European nuclear power plantsKREBS, W.-D; HOLZER, R; WINNIK, S et al.Kerntechnik (1987). 1990, Vol 55, Num 2, pp 87-93, issn 0932-3902, 7 p.Article

Local blockage calculations with the sabre codeTHOMAS, H. A; WALL, D. N.Nuclear energy (1978). 1989, Vol 28, Num 3, pp 191-200, issn 0140-4067, 10 p.Article

Flow and convective heat transfer analysis using RANS for a wire-wrapped fuel assemblyAHMAD, Imteyaz; KIM, Kwang-Yong.Journal of mechanical science and technology. 2006, Vol 20, Num 9, pp 1514-1524, issn 1738-494X, 11 p.Article

Experimental identification of turbulent fluid forces applied to fuel assemblies using an uncertain model and fretting-wear estimationBATOU, A; SOIZE, C.Mechanical systems and signal processing. 2009, Vol 23, Num 7, pp 2141-2153, issn 0888-3270, 13 p.Article

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

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

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

Homogenization-free reactor core analysis with general first collision probabilities methodPOVESCHENKO, Tamara S.Progress in nuclear energy (New series). 2004, Vol 45, Num 2-4, pp 143-152, issn 0149-1970, 10 p.Article

A numerical analysis for a BWR fuel assembly drop eventWU, Huang-Jau; TSENG, Che-Chung; CHENG, Shih-Chung et al.Journal of Nuclear Science and Technology. 2006, Vol 43, Num 9, pp 1068-1073, issn 0022-3131, 6 p.Conference Paper

Evaluation of surrogate models in optimization of wire-wrapped fuel assemblyRAZA, Wasim; KIM, Kwang-Yong.Journal of Nuclear Science and Technology. 2007, Vol 44, Num 6, pp 819-822, issn 0022-3131, 4 p.Article

A combined method to evaluate the resonance self shielding effect in power fast reactor fuel assembly calculationCHIBA, Gou.Journal of Nuclear Science and Technology. 2003, Vol 40, Num 7, pp 537-543, issn 0022-3131, 7 p.Article

MULTIOBJECTIVE OPTIMIZATION OF A WIRE-WRAPPED LMR FUEL ASSEMBLYRAZA, Wasim; KIM, Kwang-Yong.Nuclear technology. 2008, Vol 162, Num 1, pp 45-52, issn 0029-5450, 8 p.Article

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

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