Reactor engineering and equipmentUN, 1965 - Nuclear energy |
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annulus axial boiling boucle bouillante bubble burn-out calculated caléfaction CEGB channel coeficientes constant convection coolant core correlation CRITICAL HEAT FLUX curve d'échange d'essais d'une deux diameter distribution dry-out ebullición elementos combustibles éléments equation EURATOM experimental experiments Figure film flow rate fluide flujo fuel element heat transfer coefficient heating surface helical hydraulic diameter inlet kg/cm² l'écoulement liquid líquidos loop mass flow mass flow rate measured mémoire nombre Nuclear número Nusselt obtenus ont été paroi Peclet peut presión pression pressure drop radiolyse ratio réacteurs reactor resultados résultats Reynolds number steam quality subcooling temperature térmico terphényle test section thermal thermique thermocouples transfert de chaleur transmisión de calor tube tubos turbulent two-phase flow valeurs values Vapotron variation velocidad velocity vitesse void fraction wall Zircaloy были быть газа данные для жидкости кипения можно потока при реактора результаты рис скорости стержней также температуры теплоотдачи