Pascal and Francis Bibliographic Databases


Search results

Your search

kw.\*:("Reactor metal líquido")

Document Type [dt]

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Publication Year[py]

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Discipline (document) [di]

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV


A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Author Country

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Results 1 to 25 of 314

  • Page / 13


Selection :

  • and

Hydrodynamic characteristics of liquid-metal blankets of thermonuclear-power plantsKOREN', V. M; SALTYKOVSKY, A. V; FIRSOVA, E. V et al.Inženerno-fizičeskij žurnal. 1990, Vol 58, Num 2, pp 229-235, issn 0021-0285, 7 p.Article

Design of a complementary scram system for liquid metal cooled nuclear reactorsVANMAERCKE, S; VAN DEN EYNDE, G; TIJSKENS, E et al.Nuclear engineering and design. 2012, Vol 243, pp 87-94, issn 0029-5493, 8 p.Article

Seismic analysis of heavy-liquid-metal-cooled reactor vesselsBUONGIORNO, J; HAWKES, B. D.Nuclear engineering and design. 2004, Vol 228, Num 1-3, pp 305-317, issn 0029-5493, 13 p.Conference Paper

The modular reactor plantBLUMBERG, B.Proceedings of the American Power Conference. 1984, Vol 46, pp 694-695, issn 0097-2126Conference Paper

A low cost liquid metal reactor designHOWARD ARNOLD, W; ANDSERSON, C. A; MANGUS, J. D et al.Proceedings of the American Power Conference. 1984, Vol 46, pp 688-693, issn 0097-2126Conference Paper

Cost-competitive, inherently safe LMFBR pool plantMCDONALD, J. S; BRUNINGS, J. E; CHANG, Y. I et al.Proceedings of the American Power Conference. 1984, Vol 46, pp 696-700, issn 0097-2126Conference Paper

Passive safety testing at the fast flux test facilityLUCOFF, D. M.Nuclear technology. 1989, Vol 88, Num 1, pp 21-29, issn 0029-5450Article

Multiple recycling of light water reactor waste plutonium in a fast spectrum coreSEGEV, M; MISULOVIN, A; GALPERIN, A et al.Nuclear science and engineering. 1997, Vol 127, Num 2, pp 238-244, issn 0029-5639Article

Numerical investigation of multi-dimensional characteristics in sodium combustionTAKATA, Takashi; YAMAGUCHI, Akira; MAEKAWA, Isamu et al.Nuclear engineering and design. 2003, Vol 220, Num 1, pp 37-50, issn 0029-5493, 14 p.Article

Stability analysis of a liquid-metal reactor and its primary heat transport systemDEPIANTE, E. V.Nuclear engineering and design. 1994, Vol 152, Num 1-3, pp 361-377, issn 0029-5493Article

Key asset-inherent safety of LMFBR pool plantMARCHATERRE, J. F; SEVY, R. H; LANCET, R. T et al.Proceedings of the American Power Conference. 1984, Vol 46, pp 701-704, issn 0097-2126Conference Paper

Simulation of molten metal freezing behavior on to a structureMIZANUR RAHMAN, M; EGE, Yoshiyuki; MORITA, Koji et al.Nuclear engineering and design. 2008, Vol 238, Num 10, pp 2706-2717, issn 0029-5493, 12 p.Article

Thermohydraulic optimization of liquid metal self-cooled breeding blanketsKIRILLOV, I. R; VITKOVSKY, I. V.SOFT : Symposium on fusion technology. 1998, 2Vol, Vol 2, 1175-1178Conference Paper

Basic concepts for the liquid-metal target loop of accelerator-controlled reactorsBEZONOSOV, A. V; VESHNYAKOV, K. B; SEROV, V. E et al.Atomic energy (New York, N.Y.). 1996, Vol 81, Num 3, pp 647-650, issn 1063-4258Article

Hydrogen production by direct contact pyrolysis of natural gasSERBAN, Manuela; LEWIS, Michele A; MARSHALL, Christopher L et al.Energy & fuels. 2003, Vol 17, Num 3, pp 705-713, issn 0887-0624, 9 p.Article

Parametric study on fast reactors with low sodium void reactivity by the use of zirconium hydride layer in internal blanketRACHI, M; YAMAMOTO, T; JENA, A. K et al.Journal of Nuclear Science and Technology. 1997, Vol 34, Num 2, pp 193-201, issn 0022-3131Article

Design study of lead- and lead-bismuth-cooled small long-life nuclear power reactors using metallic and nitride fuelSEKIMOTO, H; SU'UD, Z.Nuclear technology. 1995, Vol 109, Num 3, pp 307-313, issn 0029-5450Article

Prospects for fast reactorsBLUMFIELD, C. W.Proceedings of the Royal Society of Edinburgh. Section B, Biological sciences. 1987, Vol 92, Num 1-2, pp 57-71, issn 0269-7270Conference Paper

LBE-water interaction in sub-critical reactors : First experimental and modelling resultsCIAMPICHETTI, A; AGOSTINI, P; BENAMATI, G et al.Journal of nuclear materials. 2008, Vol 376, Num 3, pp 418-423, issn 0022-3115, 6 p.Conference Paper

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

Nuclear power plants with lead-bismuth coolantGROMOV, B. F; ORLOV, YU. I; TOSHINSKII, G. I et al.Atomic energy (New York, N.Y.). 1996, Vol 81, Num 5, pp 770-775, issn 1063-4258Article

Sul problema di conteminento nei reattori veloci refrigerati al sodio = Problem of containment of sodium fast breederLORENZINI, G.Tecnica Italiana. 1996, Vol 61, Num 3, pp 93-97, issn 0040-1846Article

Dry patch formed boiling and burnout in potassium pool boilingMICHIYOSHI, I; TAKENAKA, N; TAKAHASHI, O et al.International journal of heat and mass transfer. 1986, Vol 29, Num 5, pp 689-702, issn 0017-9310Article

Characterization of cellular convection of argon in top shield penetrations of pool type liquid metal fast reactorsPALIWAL, Pranav; PARTHASARATHY, U; VELUSAMY, K et al.Nuclear engineering and design. 2012, Vol 250, pp 207-218, issn 0029-5493, 12 p.Article

Model development for analysis of the Korea advanced liquid metal reactorCHANG, Won-Pyo; KWON, Young-Min; LEE, Yong-Bum et al.Nuclear engineering and design. 2002, Vol 217, Num 1-2, pp 63-80, issn 0029-5493Article

  • Page / 13