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Hydrogenation, reactors safety

Lee, J.H. et al., Hydrogen-air detonations, in Proc. 2nd International Workshop on the Impact of Hydrogen on Water Reactor Safety, M. Berman, Ed., SAND82-2456, Sandia National Laboratories, Albuquerque, 1982. [Pg.567]

Hoffheins, B. S., Lauf, R. J., McKnight, T. E., Smith, R. R. and James, R. E. 1997, Evaluation of a hydrogen sensor for nuclear reactor containment monitoring, Proceedings of the International Topical Meeting on Advanced Reactor Safety, American Nuclear Society, 1 609. [Pg.162]

The explosion of combustible gas is a very severe problem to keep the reactor safety. The problem can be considered as overpressure caused by blast to the safety-related components. There are three principal countermeasures against explosion, that is, i) place a distance between the reactor and the hydrogen production system enough to mitigate the overpressure within an allowable range, ii) limit the leak amount of combustible gas, and iii) protect blast with barriers such as wall, bank and so on. As for the hydrogen production system connected to HTTR, the countcnncasure-ii) was mainly considered. [Pg.179]

THOMPSON, L., EPRI Research on Hydrogen Combustion and Control for Nuclear Reactor Safety, (4th World Hydrogen Energy Conf., Pasadena, FRG, 1982), Hydrogen Energy Progress IV (1982) 1675-1684. [Pg.61]

STAMPS, D.W., BENEDICK, W.B., TIESZEN, S.R., Hydrogen-Air-Diluent Detonation Study for Nuclear Reactor Safety Analysis, Report NUREG/CR-5525, SAND89-2398, Sandia National Laboratory, Albuquerque, USA (1991). [Pg.246]

W.C.H. Kupferschmidt, et al., The Oxidation of Cesium Iodide During Hydrogen Combustion , In Proceedings of the Third CSNI Workshop on Iodine Chemistry in Reactor Safety, Toki-Mura (Japan), 1991, Japan Atomic Energy Research Institute Report JAERI - M 92-012, p. 298 (1992). [Pg.75]

Kupferschmidt, W. C. H., Buttazoni, J. B., Evans, G. J., Harris, D. R., Greig, D. R., Koroll, G. W., Sanipelli, G. G. (d) The oxidation of cesium iodide aerosols during hydrogen combustion. Proc. 3. CSNI Workshop on Iodine Chemistry in Reactor Safety, Tokai-mura, Japan, 1991 Report JAERI—M 92—012 (1992), p. 298—310 Kupferschmidt, W. C. H., Buttazoni, J. B., Melnyk, A. J., Portman, R., Sanipelli, G. G. (a) The effects of zinc primer surfaces on iodine behaviour within containment. Proc. 3. CSNI Workshop on Iodine Chemistry in Reactor Safety, Tokai-mura, Japan, 1991 Report JAERI-M 92-012 (1992) p. 195-212... [Pg.661]

D. W. Stamps and M. Berman, A Critical Review of High-Temperature Hydrogen Combustion in Reactor Safety Applications, SAND88-0680C, International Conference on Thermal Reactor Safety, Avignon, France, October 1988. [Pg.463]

S.S. Tsai, N.J. Liparulo, Fog inerting criteria for hydrogen-air mixtures, in Proceeding of 2nd international Conference on Hydrogen Impact on Water Reactor Safety, NUREG/CP 0038, Albuquerque, 1982, pp. 727-739... [Pg.72]

S.B. Dorofeev, A.S. Kotchurko, B.B. Chaivanov, Evaluation of the hydrogen explosion hazard, in Proceedings of 18th Water Reactor Safety Meeting, 1990... [Pg.216]

J. E. Obrien, "Effects of Hydrogen Generation on Severe Accident Natural Circulation", Proceedings of the Nineteenth Water Reactor Safety Information Meeting. NUREG/CP-0180, March 1992. [Pg.483]

The short-term permeation rate of hydrogen from the ZrHi 7 layer at an accident is also calculated. The hypothetical scenario in which the temperature of the ZrHi 7 layer is suddenly increased to 1,260°C (the criterion of the cladding surface temperature at the LOCA is created, and the void reactivity is analyzed). The results are shown in Fig. 7.11. It can be seen that several hours are needed to lose one third of the hydrogen from the layer. That is much longer than the time required for the control rod insertion and borated water injection. Therefore, the hydrogen loss does not impose any severe problem for reactor safety. [Pg.452]


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See also in sourсe #XX -- [ Pg.20 ]




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