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A systematic approach to the design of a large-scale detritiation system for controlled thermonuclear fusion experimentsHEMMERICH, J. L.Fusion technology. 1993, Vol 24, Num 2, pp 137-144, issn 0748-1896Article

Operation, maintenance and decontamination of the JET torus access facilitiesEDWARDS, P; DAVIES, N; LOVING, A et al.Fusion science and technology. 2002, Vol 41, Num 3, pp 607-611, 5 p., 2Conference Paper

Long term operation of the jet facilities' active gas handling systemBRENNAN, P. D.Fusion science and technology. 2002, Vol 41, Num 3, pp 578-582, 5 p., 2Conference Paper

Design and operational experience with a pilot-scale CECE detritiation processMILLER, J. M; CELOVSKY, S. L; EVERATT, A. E et al.Fusion science and technology. 2002, Vol 41, Num 3, pp 1077-1081, 5 p., 2Conference Paper

Oxidative decontamination of tritiated materials employing ozone gasGENTILE, Charles A; PARKER, John J; GUTTADORA, Gregory L et al.Fusion science and technology. 2002, Vol 41, Num 3, pp 700-705, 6 p., 2Conference Paper

Development of a heavy water detritiation plant for PIK reactorALEKSEEV, I. A; BONDARENKO, S. D; FEDORCHENKO, O. A et al.Fusion science and technology. 2005, Vol 48, Num 1, pp 286-289, 4 p.Conference Paper

Treatment of tritiated solventsSHMAYDA, W. T; BRUGGEMAN, A; BRAET, J et al.Fusion science and technology. 2002, Vol 41, Num 3, pp 721-725, 5 p., 2Conference Paper

The ancillary systems of the European test blanket modules: Configuration and integration in TIERRICAPITO, I; BEDE, O; BOCCACCINI, L. V et al.Fusion engineering and design. 2010, Vol 85, Num 7-9, pp 1154-1161, issn 0920-3796, 8 p.Conference Paper

Tritium processing systems for the helium cooled pebble bed test blanket moduleRICAPITO, I; CIAMPICHETTI, A; AGOSTINI, P et al.Fusion engineering and design. 2008, Vol 83, Num 10-12, pp 1461-1465, issn 0920-3796, 5 p.Conference Paper

Experimental design of tritium extraction loop from lead lithium eutecticMOHAN, Sadhana; BHANJA, Kalyan; SANDEEP, K. C et al.Fusion engineering and design. 2010, Vol 85, Num 5, pp 803-808, issn 0920-3796, 6 p.Article

Conceptual design on interface between ITER and tritium extraction system of Chinese helium-cooled solid breeder test blanket moduleZHANG LONG; LUO TIANYONG; FENG KAIMING et al.Fusion engineering and design. 2010, Vol 85, Num 10-12, pp 2213-2216, issn 0920-3796, 4 p.Conference Paper

Testing of a prototype saes st909 getter bed for conditioning gas to a trituim stripper systemHSU, Robert H; HOLDER, Jeffrey S.Fusion science and technology. 2005, Vol 48, Num 1, pp 171-174, 4 p.Conference Paper

Recovery of tritium from pharmaceutical mixed waste liquidsSHMAYDA, W. T; GALLAGHER, R. D.Fusion science and technology. 2002, Vol 41, Num 3, pp 726-730, 5 p., 2Conference Paper

Operating experience of the tritium laboratory at CRLGALLAGHER, C. L; MCCRIMMON, K. D.Fusion science and technology. 2005, Vol 48, Num 1, pp 237-242, 6 p.Conference Paper

A summary of tritium in-bed accountability for 1500 liter LaNi4.25Al0.75 storage bedsKLEIN, J. E.Fusion science and technology. 2002, Vol 41, Num 3, pp 542-550, 9 p., 2Conference Paper

Development of electrochemical hydrogen pump under vacuum condition for a compact tritium gas recycling systemKATO, M; ITOH, T; SUGAI, H et al.Fusion science and technology. 2002, Vol 41, Num 3, pp 859-863, 5 p., 2Conference Paper

DEMO plant design beyond ITERKONISHI, Satoshi; NISHIO, Satoshi; TOBITA, Kenji et al.Fusion engineering and design. 2002, Vol 63-64, pp 11-17, issn 0920-3796, 7 p.Conference Paper

Recovery of tritium from different sources by the ITER Tokamak exhaust processing systemGLUGLA, M; DÖRR, L; LÄSSER, R et al.Fusion engineering and design. 2002, Vol 61-62, pp 569-574, issn 0920-3796, 6 p.Conference Paper

Tritium accounting by in-situ calorimetry of the jet uranium containersPEREVEZENTSEV, A; HEMMERICH, J.Fusion science and technology. 2002, Vol 41, Num 3, pp 797-800, 4 p., 2Conference Paper

Tritium isotope separation using adsorption-distillation columnFUKADA, Satoshi.Fusion science and technology. 2005, Vol 48, Num 1, pp 140-143, 4 p.Conference Paper

Demonstration of very high detritiation factors with a pilot-scale CECE facilityGRAHAM, W. R. C; EVERATT, A. E; TREMBLAY, J. R. R et al.Fusion science and technology. 2002, Vol 41, Num 3, pp 1137-1141, 5 p., 2Conference Paper

Design and commissioning of upgraded impurity processing system at the jet facilitiesPEREVEZENTSEV, A; BELL, A; BRENNAN, P. D et al.Fusion science and technology. 2002, Vol 41, Num 3, pp 1014-1017, 4 p., 2Conference Paper

H-D-T cryogenic distillation experiments at TPL/JAERI in support of ITERIWAI, Y; YAMANISHI, T; O'HIRA, S et al.Fusion engineering and design. 2002, Vol 61-62, pp 553-560, issn 0920-3796, 8 p.Conference Paper

The water detritiation system of the ITER tritium plantIWAI, Y; MISAKI, Y; HAYASHI, T et al.Fusion science and technology. 2002, Vol 41, Num 3, pp 1126-1130, 5 p., 2Conference Paper

A new tritium gas generator for the activity standardization of tritiated water by internal gas proportional countingSTANGA, D; MOREAU, I; PICOLO, J. L et al.Fusion science and technology. 2005, Vol 48, Num 1, pp 354-357, 4 p.Conference Paper

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